ML20095L146

Seismic Evaluation Rept for USI A-46, Rev 0

ML20095L146
Person / Time
Site:	Crystal River
Issue date:	01/02/1996
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20095L145	List: 3F1295-18, Forwards Crystal River Unit 3 Seismic Evaluation Rept for USI A-46, Rev 0 ML20095L146
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR NUDOCS 9601020070
Download: ML20095L146 (242)

Text

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FLORIDA POWER CORPORATION I

CRYSTAL RIVER UNIT 3 .

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[g SEISMIC EVALUATION REPORT i FOR

! UNRESOLVED SAFETY ISL UE A-46 PDR Revision 0

CONTENTS f

- Ease 1.- In trod uction ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Pu rpose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2 Plant Description ................................... 1 1.3 Bac kg round . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.4 Report Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

2. Safe Shutdown Earthquake . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.1 Ground Response Spectra .............................. 5 2.2 In-Structure Response Spectrum ....... 1................. 6

.E Figure 2-1: Design Acceleration Spectra for CR3 . . . . . . . . . . . . . . . . . . . . 8 Figure 2-2: Maximum Hypothetical Acceleration Spectra for CR3 .........9 q Figure 2-3: Response Spectrum for De 'gn for CR3 . . . . . . . . . . . . . . . . . 10 L/ Figure 2-4: GIP Bounding and Reference Spectra versus CR3 Plant Spectra . . 11

3. Project Team .........................................12 3.1 Utility Representatives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.2 Seismic Capability Engineers . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.3 Third-Party Auditors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13

4. Safe Shutdown Equipment List (SSEL) . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.1 Basic Criteria and Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.2 Methodology for Developing SSEL . . . . . . . . . . . . . . . . . . . . . . . 17 4.3 Description of Safe Shutdown Path (s) . . . . . . . . . . . . . . . . . . . . . . 18 4.3.1 Reactor Reactivity Control . . . . . . . . . . . . . . . . . . . . . . . . 18 hm C

4.3.2 Reactor Coolant Pressure Control . . . . . . . . . . . . . . . . . . . . 19 4.3.3 Reactor Coolant Inventory Control . . . . . . . . . . . . . . . . . . . 20 4.3.4 Decay Heat Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 4.4 Electrical and Mechanical Support Systems for Hot Shutdown . . . . . . . 23 4.5 Description of Safe Shutdown Equipment Lists . . . . . . . . . . . . . . . . 27 4.6 Operations Review of SSEL . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 Figure 4-1:~ Safe Shutdown Alternatives for Reactor Reactivity Control .............................31 Figure 4-2: Safe Shutdown Alternatives for Reactor Coolant Pressure Control . . . . . . . . . . . . . . . . . . . . . . . . . 32 i Figure 4-3: Safe Shutdown Alternatives for Reactor Coolant Inventory Control ........................33

- Figure 4-4: Safe Shutdown Alternatives for Decay Heat Removal . . . . . . . . 34

5. Mechanical and Electrical Equipment Review . . . . . . . . . . . . . . . . . . . . . . 35 5.1 Summary of Review .................................35 .

5.1.1 Seismic Capacity vs. Demand . . . . . . . . . . . . . . . . . . . . . . 35 5.1.2 Equipment Class Descriptions . . . . . . . . . . . . . . . . . . . . . . 36 i 5.1.3 Equipment Anchorages .........................'. 36 5.1.4 Seismic Interaction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 1

5.2 Instances of Intent but Not Letter of Caveat Met ...............36 )

l 5.3 Summary of Outliers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37

! Table 5-1 . Response Spectrum Exceedances for Building Elevations . . . . . . 38 Table 5-2 Effective Grade for Plant Structures ..................39 J

Table 5-3 Equipment Intent but Not Letter of PSP Caveat Summary . . . . . 40 l

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Table 5-4 Equipment Outlier Description and Resolution Summary . . . . . . 43 Cy V Table 5-5 List of Inaccessible Items . . . . . . . . . . . . . . . . . . . . . . . . . 54 Table 5-6 Equipment Class Distribution -

Mechanical and Electrical Equipment ............. 57-

6. Tanks and Heat Exchanger Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 6.1 Summary of Review ................................58 6.2 Summary of outliers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 Table 6-1 Tank and Heat Exchanger Outlier Description and Resolution Summary . . . . . . . . . . . . . . . . . . . . . 60

7. Cable and Conduit Raceway Review . . . . . . . . . . . . . . . . . . . . . . . . . . .

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8. Plan for Addressing Unresolved Outliers ........................63

9. Significant or Programmatic Deviations from the PSP . . . . . . . . . . . . . . . . 64

10. Third Paity Audit Summary . . .............................65

11. References . ....... .................................66 Appendix A Resumes for Seismic Capability Engineers Appendix B Composite Safe Shutdown Equipment List (SSEL)

Appendix C Screening Verification Data Sheets (SVDS)

Appendix D Third Party Audit Reports t

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.l. Introduction 1.1 Purpose (

l The purpose of this report is to document the seismic evaluation performed to address Unresolved Safety Issue (USI) A-46 at Crystal River Unit 3. This evaluation was performed using Florida Power Corporation's Plant Specific Procedure (PSP - Reference 2) for resolving USI A-46. The Plant Specific Procedure used for seismic verification for Crystal River Unit 3 (PSP Revision 1) was formally submitted to the NRC on September 16,1994 (Reference 11).

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1.2 Plant Description Crystal River Unit 3 is comprised of one nuclear power unit and uses a pressurized water reactor. Babcock and Wilcox designed and furnished the Nuclear Steam Supply System (NSSS) equipment and systems, including the fuel assemblies. Florida Power Corporation contracted with Gilbert / Commonwealth for engineering of the plant. >

l 1.2.1 Site Characteristics .

The 4,738 acre site is characterized by a 4,400 foot minimum exclusion radius centered on the Reactor Building; isolation from nearby population centers; sound foundation for structures; an abundant supply of cooling water; an ample supply of emergency power; j i and favorable conditions of hydrology, geology, seismology, and meteorology.

I Supply of emergency power at Crystal River Unit 3 include the following sources of electric power:

a. The generator has the capability to feed its own auxiliaries. Upon a trip

separating the substation from the transmission system, the turbine-generator is designed to stay in operation, supplying power to the unit auxiliary buses.

b. Five 230 kv transmission lines - two being fed from Brooksville, two being

supplied from Central Florida, and one from Fort White.

c. Either Unit 1,2,4, or 5 at Crystal River Complex. l

d. Two' quick starting 3,000 kw diesel-generator units connected to the Engineered i Safeguards (ES) buses. l 1.2.2 Power Level i l

, The operating level of the reactor is 2544 MWt. An application with the NRC is

pending to upgrade the power level to 2568 MwT.

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1.3 Background

. Because of the extent of the changes in the requirements for seismic qualification of equipment over the years, the U.S Nuclear Regulatory Commission (NRC) initiated i Unresolved Safety Issue (USI) A-46, " Seismic Qualification of Equipment in Operating 4 Nuclear Plants," in December 1980. The purpose of USI A-46 is to verify the seismic adequacy of essential equipment in operating plants which had not been qualified in

accordance with more recent criteria.

In 1982, the Seismic Qualification Utility Group (SQUG) was formed to develop a

) practical approach for seismic qualification of equipment in operating plants. The approach developed by SQUG was to use experience with the performance of power plant and industrial equipment in actual earthquakes as the primary basis for evaluating the seismic ruggedness and functionality of essential equipment in nuclear power plants.

In 1983, the NRC issued NUREG 1018 which includes a general endorsement of the use of experience data for verification of the seismic adequacy of equipment in nuclear plants.

In early 1987, the NRC issued Generic Letter (GL) 87-02 (Reference 1) to owners of i operating nuclear plants which were licensed prior to the development of modern seismic qualification standards. The rxipients of GL 87-02 are referred to as A-46 plants and 4 include Crystal River Unit 3. Essentially, all owners of A-46 plants, including Florida

< Power Corporation, are SQUG members. GL 87-02 requires plant owners to take action to verify the seismic adequacy of important equipment in their plants. The SQUG approach embodied in the Generic Implementation Plan (GIP)is explicitly recognized by 5

the NRC as the preferred method for accomplishing this objective.

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l. On October 7,1988 Florida Power Corporation sent a letter to the NRC (Reference 9) stating that as a member of EPRI and SQUG, Florida Power Corporation has supported the many efforts on which the GIP is based. Florida Power Corporation further stated that Florida Power Corporation would review the final GIP after approval by the NRC t and resolution of all outstanding issues. Based on this review, Florida Power j Corporation stated that they would file a plant-specific response based on generic 4 resolution of USI A-46. In that plant-specific response, Florida Power Corporation said that they may elect not to perform certain aspects of the generic program and may 4 modify aspects based upon suitablejustification including the low seismic hazard existing at Crystal River Unit 3.

In 199.1, the NRC issued Supplement Number 1 to GL 87-02 (Reference 4) which transmitted Supplemental Safety Evaluation Report No. 2 on SQUG GIP, Revision 2, as correct:d on February 14,1992 (Reference 5).

J In mid 1994,- Florida Power Corporation contracted Dr. Paul Smith of the Readiness Operatton and Mr. Harry Johnson of Programmatic Solutions to prepare a document that

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I i provides justification for Florida Power Corporation to deviate from the " letter" of the GIP. This document is titled " Technical Basis for the Crystal River Unit 3 Plant Specific l j Procedure to Resolve NRC Generic Letter 87-02", Reference 6. l

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j From this report, Florida Power Corporation prepared a " Plant Specific Procedure (PSP) I j for Seismic Verification of Nuclear Plant Equipment," (Reference 2). This document has l been forwarded to the NRC on August 27, 1994. The NRC subsequently issued a Request for Information, Reference 7. Florida Power Corporation provided a response to the Request for Information (Reference 10) and transmitted Revision 1 of the PSP

(Reference 11) which includes changes identified in Reference 10 to the Nuclear Regulatory Commission.

1.4 Report Organization s

The remaining sectior.; of thi treport are organized in accordance with Section 9.4 of the j PSP, Reference 2. These sectiens include the following: ,

e In Section 2, " Safe Shutdown Earthquake", the Crystal River Unit 3 Ground i

Response Spectra (GRS) and In-Structure Response Spectra (IRS) are described, i The bases for determining how seismic demand is determined for each equipment

[ are provided in Section 5, and documented on the Screening Verification Data Sheets (SVDS) forms in Appendix C in this report.

e In Section 3, " Project Team", the Crystal River Unit 3 project team is described.

l 7j Resumes for Seismic Capability Engineers (SCE) are included in Appendix A of

. this report.

'r e In Section 4, " Safe Shutdown Equipment List," there is information describing

! the safe shutdown path selection, plant operation procedures used, and Crystal

! River Unit 3 Operations Department review of the SSEL. The list of equipment on the SSEL is included in Appendix B. ,

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• In Section 5, " Mechanical and Electrical Equipment Review," screening l verification and walkdown results for mechanical and electrical equipment are

! discussed, in addition to the SVDS forms provided in Appendix C. Instances in which the use of a caveat is met without meeting the specific wording of the l caveat rule are identified. A summary of outliers and their resolution is provided.

e In Section 6, " Tanks and Heat Exchanger Review," results of the tanks and heat l exchanger review are described, including instances in which the intent, of a i caveat is met. A summary of outliers and their resolution is provided, e In Section 7, " Cable and Conduit Raceway Review," a summary is provided of f

f the method used for the Crystal River Unit 3 PSP.

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I e- In Section 8, " Plan for Addressing Unresolved Outliers," the plan and schedule for addressing the remaining outliers is provided.

e In Section 9, "Significant or Programmatic Deviations from the PSP," a statement is made that no significant or programmatic deviations from the Crystal River Unit 3 PSP are made, e In Section 10, " Third-Party Audit Summary", the audit is summarized, including resolution of recommendations made by the auditor during the initial audit. The audit report is included in Appendix D. l 4

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! 2. Safe Shutdown Earthquake O

lV 2.1 ' Ground Response Spectra 1 This section gives information on the Crystal River Unit 3 Ground Response Spectra.

I The following information comes directly from the Crystal River Unit 3 Final Safety Analysis Report (FSAR - Reference 8).

' "The nearest faulting occurs at a distance of three miles to the east of the site.

7 Stratigraphic correlation and continuity of seismic refraction profiles negate the possible i existence of subsurface faults at the site."

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... The seismic study was performed by Weston Geophysical Research, Inc., who conducted a thorough literature search and examined available seismographs to determine

the epicentral distribution of earthquakes in the southeastern United States, their focal depth, intensity and/or magnitude, and attenuation characteristics. Regional tectonics and

fault patterns were investigated for possible association with known epicenters. This study indicated that the State of Florida is seismically inactive, and that the closest area to the site of significant seismic activity is Charleston, South Carolina. Attenuation data available for this area indicates that the site experienced an observed intensity no higher i than Intensity V (Modified Mercalli). The maximum ground motion at the site due to <

this earthquake probably did not exceed 0.025g. For design purposes the maximum ground acceleration was assumed to be 0.05g. Response spectra were developed for the site normalized for a maximum ground motion of 0.05g and based upon a large j

'O- earthquake in the Charleston, South Carolina region and moderate earthquakes in Florida."

1 "2.5.4 SEISMOLOGY" I "The seismicity analysis and response spectra were conducted by Weston Geophysical i- Research, Inc. Reverend Daniel Linehan, S.J., Director of Weston Observatory, acted

as consultant on the seismicity analysis. The response spectra was completed by Dr.

Allin Cornell, Department of Civil Engineering, Massachusetts Institute of Technology."

4 "2.5.4.1 Seismicity Analysis"

!' "The State of Florida is an area which is consistently seismically inactive. In a 300-year history, only eight earthquakes of Intensity IV (Modified mercalli) er greater have had

j. their epicenters located within the State. No carthquake is known to have occurred within 50 miles of the plant site."

j "The two strongest earthquake to have affected the site area in north central Florida, 1 were the North Florida Earthquake of January 12,1879, listed as Modified Mercalli VI; and the Charleston, South Carolina Earthquake of 1885 which had an epicentral intensity

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X, Modified Mercalli. There is no evidence that seismic activity in the southern n Appalachians or in the Greater Antilles Islands of the West Indies had any effect on the U Crystal River site."

"An attenuation curve or earthquake intensity with distance for the Atlantic and Gulf

~ Coastal Plains indicates rather slow attenuation ofintensity with distance, due apparently to the deep Cretaceous sediment areas of the Coastal Plains regions. Based upon this

' attenuation data, the Florida earthquake of 1879 would have produced an intensity no higher than the Modified Mercalli IV at the site; and the Charleston earthquake of 1885 would have had an intensity no higher than V at the Crystal River site." l

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" Based upon the relationship between earthquake intensity and ground acceleration given  ;

I in Nuclear Reactors and Farthqukes TID-7024, United States Atomic Energy

Commission, the Charleston, South Carolina earthquake would have resulted in a ground acceleration of approximately 0.025g at the site. A design value of 0.05g, or double the estimated acceleration from the history of the site, is considered conservative."

"2.5.4.2 Resoonse Spectra" ,

"The complete design response spectra was developed for the maximum ground acceleration of 0.05g, and considered earthquake magnitude and duration, epicentral i distance and focal depth, the intervening material through which the seismic waves ~

propagate,and geologic conditions local to the site."

"The shapes of the spectra were estimated by two methods, one adjusting the average strong motion spectra for moderate distances computed by Housner, and another by 3

application of a method developed by Estere and Rosenbleuth. The resulting design response spectra represent the estimated spectra coinciding with established ground acceleration level of 0.05g, and are shown on Figures 2-35 and 2-36. Seismic design

spectra for maximum hypothetical earthquake is shown in Figure 2-37."

2.2 In-Structure Response Spectrum The buildings containing SSEL equipment are the following:

1. Reactor Building: Post-tensioned concrete shell exterior with reinforced concrete and steel frame interior structures.

2. Auxiliary Building: Reinforced concrete building with steel roof support structure. Interior reinforced concrete and steel frame structures.

3. Control Complex: Reinforced concrete building with interior reinforced concrete and steel frame structures.

4. Emergency Diesel Generator Building: Reinforced concrete building with interior n reinforced concrete and steel frame structures.

(_) 5. Intermediate Building: Reinforced concrete building with interior reinforced ,

concrete and steel frame structures.

6. Emergency Feedwater Tank

Enclosure:

Reinforced concrete building with interior reinforced concrete and steel frame structures.

7. Turbine Building: Steel frame building with interior concrete and steel frame structures.

Prior to 1973, in accordance with industry practices, major components and equipment for Crystal River Unit 3 were qualified using a response spectrum equivalent to the Ground Response Spectrum (GRS) scaled by a structural response factor. In 1973, Floor Response Spectra (FRS) were developed for all plant buildings at major floor elevations.

They were developed using a response spectrum technique outlined by Biggs and Roesset in 1969 in a technical paper " Seismic Analysis of Equipment Mounted on Massive Structure."

The Crystal River Unit 3 in-structure spectra are less than the SQUG Reference Spectrum, except around about 11 Hz to 19 Hz at Auxiliary Building elevation 162 (67 feet above free field) and at the Reactor Building elevations above 160 feet (65' above r free field), see Figure 2-4 and about 9Hz and higher of the interior concrete of the

( Reactor Building for elevation 160 and higher. Only two SSEL items in the Reactor Building (RCV-10 and RCV-11) are above this elevation. Only four SSEL items in the Auxiliary Building (one solenoid valve (Class 8B), one flow transmitter (Class 18), and two air handler associated items (Class 10)) are located at elevations where the Crystal  :

River Unit 3 in-structure spectra exceed the SQUG Reference Spectra. These six items  !

. are considered as outliers to be treated later.

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3. Project Team

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( All Crystal River Unit 3 USI A-46 work was performed by Florida Power Corporation personnel, assisted by outside engineering consultants. The Project team was organized and managed as a combined effort of Florida Power Corporation Licensing Department (Mr. Al Friend) and Structural Engineering (Mr. Glenn Pugh).

Plant walkdowns were performed by Seismic Capability Engineers who meet the training, educational, and experience qualifications of Section 2 of the PSP). Plant walkdowns were performed in the following time frames:

1. From April 1994 to June 1994: Selected equipment in the reactor building

2. March 1995: Most accessible non-intrusive walkdowns

3. September 1995: Most accessible intrusive walkdowns I

4. March 1996 (planned): Outage walkdown of remaining items inaccessible during previous walkdowns.

Preparation of the Safe Shutdown Equipment List (SSEL) was performed by Florida Power Corporation personnel.

(3 3.1 Utility Representatives V

The overall coordination and responsibility for completion of the A-46 effort was performed by Mr. Al Friend of the CR3 Licensing Department. Mr. Friend was instrumental in the development of the SSEL. Mr. Friend is the Florida Power Corporation SQUG Representative.

Engineering efforts were lead by Mr. C. Glenn Pugh of the CR3 Structural Engineering Department. Mr. Pugh had responsibility for the preparation of the PSP (Reference 2) and associated Technical Basis Document (Reference 6). Mr. Pugh led one walkdown team and had the responsibility for walkdown implementation and completion. Mr. Pugh is the Florida Power Corporation Alternate SQUG Representative.

Mr. Ken Vogel is the Supervisor of Operations Engineering and was responsible for the Operations review of the SSEL. The review was conducted by Mr. Leon Gagne, an Assistant Shift Supervisor and Licensed Senior Reactor Operator.

3.2 Seismic Capability Engineers The following Florida Power Corporation staff have received the SQUG certified training and meet the requirements for " Seismic Capability Engineer."

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Anthony Petrowsky, Supervisor Nuclear Engineering i

~Q Daniel L. Jopling, Senior Nuclear Structural Engineer Joe A. Iese, Senior Nuclear Structural Engineer i k/

, C. Glenn Pugh, Senior Nuclear Structural Engineer

John O. Mascoll, Project Engineer B

Mr. Pugh led one walkdown team with Mr. Mascoll performing the duties of Seismic Capability Engineer for that tes.m.

The following consultants were contracted by Florida Power Corporation to assist in performing the seismic screening walkdown.

I Paul Smith, The Readiness Operation, Inc.

3 Harry Johnson, Programmatic Solutions, Inc.

Donald Rutherford, Programmatic Solutions, Inc.

l ' Resumes for Seismic Capability Engineers are provided in Appendix A.

3.3 Third-Party Auditors The third-party audit of the Crystal River Unit 3 A-46 work was performed by Mr. Charbel Abou-Jaoude of VECTRA Technologies.

Mr. Abou-Jaoude's resume is provided in Appendix A and his report is in Appendix D.

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- 4. Safe Shutdown Equipment List (SSEL)

The SQUG Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment (Reference 5) provides guidance for identifying the various alternate methods,' or paths, to be used in accomplishing the following safe shutdown functions subsequent to a safe shutdown earthquake (SSE):

• Reactor Reactivity Control e Reactor Coolant Pressure Control j~ e Reactor Coolant Inventary Control e Decay Heat Removal 2

The purpose of this section is to document those methods that were used to identify those safe shutdown paths and components that are needed _ to accomplish the four safe

shutdown functions at Crystal River Unit 3 (CR3). This section, along with FPC Plant

{ Specific Procedure (PSP) For Seismic Verification of Nuclear Plant Equipment satisfy the SQUG commitment to provid6 a Safe Shutdown Equipment List (SSEL) Report. This j section includes the Composite SSEL, and Seismic Review Listing as well as the overall approach used to develop them.

i The methodology used to identify the safe shutdown paths and components is in 4 accordance with the PSP except as noted herein. Using the guidelines provided in the l

PSP, and CR3 operating procedures and flow drawings, FPC has identified those systems and safe shutdown paths which can be used to accomplish the four safe shutdown j functions. An overview of the basic approach taken to accomplish each of these shutdown functions is shown on Figures 4-1 through 4-4 In addition to the systems i needed to directly perform the above functions, those support systems that will be needed to conduct a safe shutdown have also been identified herein.

In selecting the paths that could be used to conduct a safe shutdown, FPC reviewed the flow drawings for the systems associated with maintaining the four safe shutdown functions and the Normal and Emergency Operating Procedures for CR3. As a result, i- the paths selected are similar to those used to shutdown the plant following other events and should result in little, or no, procedural changes for the plant. Operator actions

! which may need to be taken to compensate for equipment or system failure, and are considered out of the normal routine, are addressed in Section 4.3.

1 l 4.1 Basic Criteria and Assumptions The methodology used to select the safe shutdown path and equipment needed for a safe i shutdown function utilizes certain criteria and makes certain assumptions. These criteria i and assumptions are identified in the following:

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4.1.1 Generic Criteria and Assumptions J The generic criteria and assumptions used to select the safe shutdown paths and

equipment are listed in PSP Sections 3.1.2 and 3.2. Some of the more significant criteria -

and assumptions used are-

1. The safe shutdown equipment should not rely upon offsite power. Offsite power may not be available for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following a design basis SSE. All identified equipment needing electrical power should be powered by the diesel generators or station batteries.

2. No other extraordinary events or accidents (e.g. LOCAs, HELBs, fires, floods, extreme winds, sabotage) are postulated to occur during the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period other

than the earthquake itself and loss of offsite power.

t

3. If achieving and maintaining safe shutdown is dependent on a single item of i equipment whose failure to perform its active function, either due to seismic loads i or random failure, would prevent accomplishment of any of the four essential j safe shutdown functions, an alternate path to safe shutdown by use of a different train or a different item of equipment in the same train will be identified for seismic evaluation.

[ 4. The safe shutdown systems chosen are of minimal complexity and effort to operate.

3

5. The safe shutdown systems chosen are consistent with the normt.1 and emergency operating procedures which are used to bring the plant to a safe shutdown

condition following a loss of off-site power.

l 6. Operator action is permitted, if necessary, to accomplish the safe shutdown function provided that sufficient manpower and time are available and proper

procedures are in place.

p j 7. Prior to the occurrence of an SSE, the unit was assumed to be at normal

operating conditions. That is, the reactor coolant system was at or near normal operating pressure and temperature.

8. If an item of equipment is taken out of service for maintenance, then that item of equipment was considered the single equipment failure.

9. The following equipment types are identified for seismic evaluation:

e Active mechanical and electrical equipment which operates or changes

state to accomplish a safe shutdown function.

i O-o 15 9

l e - Active equipment in systems which support the operation of identified safe

'p shutdown equipment; e.g., power supplies, control systems, cooling L/ systems, lubrication systems.

e Instrumentation needed to confirm that the four safe shutdown functions have been achieved and are being maintained.

o Instrumentation needed to operate the safe shutdown equipment.

e Tanks and heat exchangers used by or in the identified safe shutdown

path. Heat exchangers which are a part of the operating cooling system flow path but not required to function were also included in the evaluation. Additionally, the waste gas decay tanks were included in the j evaluation at NRC request to aid in resolution of USI A-40, Seismic Design Basis, for Crystal River 3.

- 10. The following equipment types are D01 identified for seismic evaluation:

! e Equipment which could operate but does not need to operate and which, r upon loss of power, will fail in the desired position or state without a relying on mechanical movement. This type of equipment is defined as passive for the purposes of this section.

! e Passive equipment such as piping, filters, and electrical penetration

assemblies.

g e Self-actuated check valves and manual valves.

e Major items of equipment in the Nuclear Steam Supply System (NSSS),

their supports, and components mounted on or within this equipment such t

as the reactor pressure vessel, reactor fuel assemblies, reactor intgrnals, j control rods and their drive mechanisms, reactor coolant pumps, steam ,

4 generators, pressurizer, and reactor coolant piping.

! 11. Relief valves credited for providing over-pressure protection of a safe shutdown path are considered to be passive and are not included on the SSEL. Only those relief valves which may be challenged (i.e., become active) as a result of a

. transient during the recovery from the seismic event are included on the SSEL.

. Relief valves not included in the above are considered either as an in-line component (such as a manual valve) or would be included with the parent

. component by the " rule of the box".

12. Any equipment not included on the Safe Shutdown Equipment List (SSEL) should be assumed to be not available for plant shutdown.

16 l

1

. . -- . - - .- - .. - - - = .

13. Components selected for use in performing a safe shutdown may include non-safety grade equipment.

4.1.2 Plant Specific Assumptions 1

i 1. The unit will be brought' to and maintained in a hot standby condition for 72 i hours following an SSE. Hot standby is defined by plant Technical 1 Specifications.

L

2. Redundant components are specified where required to assure that any single failure of an SSEL component can be accommodated by.use of a redundant ,

i component or train. When applicable, components are specified that are required ,

to valve in a redundant train of a filter or heat exchanger assuming the primary train has to be taken out of service.

l 3. An equipment failure is defined as the loss of the active functional capability of I the equipment, not its structural integrity. (e.g., it is not necessary to consider

rupture or leakage of fluid from a valve as a credible failure mechanism).

4 4. Certain types of equipment are inherently rugged and need not be evaluated for j seismic adequacy in the USI A-46 program. This applies to self-actuating check '

valves without external actuators, manually operated valves, pressure and temperature gauges, flow elements and other items defined in the PSP.

5. Tanks, heat exchanges, coolers, and other passive components which could fail and affect the safe shutdown function following a SSE are identified for seismic evaluation.

l 6. Instrumentation, control, and relay cabinets which could fail and affect the safe shutdown function following a SSE are also identified for seismic evaluation.

[

3 Relays associated with safe shutdown equipment are contained in these cabinets i and are evaluated (but not specifically identified) as part of the cabinet evaluation.

i

4.2 Methodology for Developing SSEL The systems and equipment required for achieving and maintaining the safe shutdown as

! identified by the PSP are those which provide the following primary functions:

I  :

a. Reactor Reactivity Control

, b. Reactor Coolant Pressure Control

c. Reactor Coolant Inventory Control

d. Decay Heat Removal 2

'O 17

v  !

f

1 The first step in the process was to identify the systems, both preferred and alternate that f' would be relied upon to achieve each of these safe shutdown functions. This was accomplished by reviewing Normal and Emergency Operating Procedures, Safe Shutdown System Flow Drawings, Electrical Distribution System Drawings, System Descriptions, and Design Basis Documents. . The knowledge of experienced plant staff was heavily drawn upon for the selection. Once these systems were identified the next step was to identify the required supporting systems. This was performed by reviewing Electrical One-Line Diagrams, Wiring Diagrams, and Normal Operating Procedures.

Once all primary and supporting systems were identified, the next step was to identify the equipment and instrumentation in each system required to achieve the four shutdown j functions. This was accomplished by reviewing the following documents.

I i a. Electrical one line diagrams

b. Elementary wiring diagrams

c. Normal operating procedures

d. Emergency and abnormal transient procedures

e. System design descriptions

f. Flow drawings The system components and instrumentation resulting from this document review are identified in the composite SSEL (Appendix B).

4.3 Description of Safe Shutdown Path (s)

The following is a description of the systems and means by which each of the primary safe shutdown functions are accomplished at CR-3 for USI A-46 evaluation. Drawings which illustrate the safe shutdown paths are included in Figures 4-1 to 4-4.

4.3.1' Reactor Reactivity Control (Figure 4-1)

The reactor reactivity control function is necessary to ensure that the reactor core achieves and maintains a subcritical condition following a SSE. The primary method for reactivity control is by the insertion of the control rods into the core shortly after obtaining the signal to shutdown. A second method is the addition of liquid neutron poison (borated water) to the reactor coolant. This method takes a longer time than control rod insertion to make the core subcritical and is not capable of performing a rapid shutdown of the reactor. Therefore, the control rods and associated control rod insertion mechanism are considered the primary means to perform the initial reactivity control function. .

The primary path for the reactivity control function is con rol rod insertion into the core upon receipt of either a manual or automatic trip sign:1 generated by the Reactor

. Protection System. Reactor trip is achieved by removing the power supply to the control

!' rods. Breakers to the control rods can be tripped from the control room or locally at the switchgear. No single failure will inhibit the protective action of the rod drive control system. The alternate path for control rod insertion can be achieved by using the trip 18

, __ __._ .__ _ _ ___._ _ d

t y

!' push button. The control rod drive motors will lose power following a loss of offsite ,

power. This will result in the release and insertion of the control rods. Short-term reactivity control is, therefore, attained.

In addition to control rod insertion, long term reactivity control, if required, can be-

- established by the addition of borated water from the borated water storage tank (DHT-1) to the Reactor Coolant System (RCS) through the makeup system. Long-term reactivity control is maintained by inventory addition from the DHT-1, which is sufficiently borated to maintain the required shutdown margin.

- If there is no Reactor Coolant System (RCS) leakage or shrinkage while the plant is maintained in hot standby, long-term reactivity control is maintained by the use of

. letdown flow and the use of borated water from the boric acid storage tanks (CAT-5A and CAT-5B). If there is significant RCS leakage and shrinkage of the RCS volume, the make-up tank and DHT-1 will be the water source to achieve the long-term reactivity control. Since make-up pump MUP-1B is selected for the primary path for long-term reactivity control function. Make-up pumps MUP-1A and 1-C are the backup path.

Verification of reactor control rod insertion is accomplished by wide range neutron flux l monitoring NI-1-A3, NI-2-B3, NI-3-C3, and NI-4-D3. An alternative to measuring 1 neutron flux directly is to measure other parameters which can be used to show that the i core remains subcritical. Measurements could be made of the position of all the control i rods, the temperature of the reactor coolant cold leg, and the boron concentration in the reactor coolant system, to assure the reactor remains subcrib.11, i

4.3.2 Reactor Coolant Pressure Control (Figure 4-2) i The main method of reactor coolant (primary) pressure control is through control of a steam space in the pressurizer. Control of the steam bubble is achieved primarily through the use of pressurizer auxiliary spray and pressurizer heaters. The principal 1 l means of decreasing RCS pressure is through the use of pressurizer auxiliary spray valves (RCV-13). To increase pressure, the pressurizer heaters are used. The

pressurizer heaters can be powered from the emergency diesel generators in the event of 1 a loss of offsite power. There is sufficient redundancy in the pressurizer heaters and associated power sources such t!iat no single active failure can disable a sufficient number  ;

! of pressurizer heaters to cause a loss of the pressure control function.

An alternate path for reducing the RCS pressure, is to open the PORV (RCV-10). In addition, Pressurizer Code Safety Valves will automatically open to limit RCS pressure below ASME Code allowable limits, however, overpressure protection is not expected  ;

to be needed in this scenario. During Decay Heat Removal System operation at low pressure, the DHR safety valve provides overpressure protection RCS pressure is also affected by the control of injection of water into the RCS via the

. MUPS, HPI, or LPI during low pressure operation and by the control of letdown and

~

seal water return from the RCS. These operations are discussed in 4.3.3 " Reactor 19 r

i I

.. l

< Coolant Inventory Control". RCS pressure is also affected by the amount of decay heat removal from the RCS. This function is discussed in 4.3.4 " Decay Heat Removal".

cy  !

Process variables which can be measured for monitoring the reactor coolant . system pressure include reactor coolant pressure, reactor coolant temperature or subcooling

margin, and pressurizer level if pressurizer heaters are used for pressure control.

. 4.3.3 Reactor Coolant Inventory Control (Figure 4-3)'

! The reactor coolant inventory control function is necessary to assure that the reactor core i remains covered so that decay heat can be removed, and to maintain a level in the

! pressurizer so that the pressurizer heaters can maintain RCS pressure control during and after the postulated earthquake. Reactor coolant inventory is controlled by isolating the

! boundary of the reactor coolant system and supplying water via the make-up system.

Inventory control has 2 elements which should be accomplished: i 5

a. . Loss of reactor coolant from the reactor coolant system should be minimized.

i

b. Sufficient make-up capacity.should be available to compensate for losses due to l

leakage from the reactor coolant system and for fluid shrinkage when the reactor coolant temperature is lowered.

The make-up and letdown functions of the make up and purification system are normally needed to control the reactor coolant inventory and maintain the pressurizer level within

!p V its operating range. There are 3 make-up pumps and 5 injection paths for the make-up

i. system. Since make-up pump MUP-1B is selected for normal plant operation, make-up

pump MUP-1B and the associated flow path is selected as the primary path. The make-  ;

up tank (MUT-1) and the borated water storage tank (DHT-1) are used as the source of water supply for this system.

4.3.3.1 Make-up for Inventory Control (Figure 4-3)  ;

The make-up system provides increases in reactor coolant inventory to maintain pressurizer level using either the normal make-up flow path or any of the high pressure seal injection flow paths.

L j Make-up pumps MUP-1 A,1B and 1C are aligned for seal injection and normal make-up.

At least one make-up pump is required to provide the flow.

MUP-1B is normally operating to provide make-up and seal injection. The make-up i pump (s) will initially take suction from the make-up tank MUT-1. Suction will be switched to the borated water storage tank for additional water inventory as the make-up j - tank inventory is depleted.-

In addition to providing inventory control, the make-up system supplies water for seal

p

v injection, the preferred method of protecting reactor coolant pump (RCP) seals. If seal injection is not available from the make-up system, another acceptable method of 20 l

1

\

maintaining seal integrity is by providing pump thermal barrier cooling from the Service j Water system.

(q ,

./

4.3.3.2 Letdown for Inventory Control (Figure 4-3)

The letdown capability will greatly simplify reactor inventory control. Manual control  !

j' of components is required to achieve and control the letdown flow. Sufficient time is I available to line up the necessary components. The letdovcn flow path requires the j l letdown coolers, pressure reduction, and the make-up tank and/or borated water storage i tank.

l

! The Service Water system must be available for the letdown coolers MUHE-1 A, IB, or

! IC if letdown is used with reactor coolant temperature above 135'F. If cooling is not available, making letdown impossible, RCP seal injection flow w!!' gradually fill the

reactor coolant system. The seal injection can be isolated by closing valve MUV-16 or by stopping all make-up pumps. MUV-16 will fail to its open position following the loss of instrument air. l 1  !

The supporting systems for the make-up and letdown functions are the decay heat closed )

cycle cooling system, and the nuclear service closed cycle cooling system. The decay

heat cic sed cooling system provides cooling for pump motor and bearing of the make-up pumps MUP-1 A and IC. If either train of the decay heat closed cycle cooling system is not available, the nuclear services closed cycle cooling water system can be aligned by manual valves to provide cooling for either make-up pump MUP-1A or IC. The

( nuclear services closed cycle cooling system provides cooling for pump motor and bearing of the make-up pump MUP-1B. The cooling system is needed for heat removal from the letdown coolers, and to provide RCP thermal barrier cooling as a backup for reactor coolant pump seal injection.

The RCP seal return capability will minimize the amount of seal water discharging to the reactor building sump and the system will be used ifit is available. Isolation of the seal return and letdown flow will limit the RCS inventory loss. The seal return and letdown lines are isolated by the closing of MUV-018 and MUV-049 respectively. The closure of these valves could be achieved by operator actions from the control room or automatic actions. MUV-018 will fail to its closed position following the loss ofinstrument air and the depletion of its 10 minute backup air accumulator if the operator does not take manual action in this time period. MUV-049 will closs on high letdown cooler outlet temperature, or it will fail closed on loss of instrument air if the operator does not take manual action.

Process variables which can be measured for monitoring the inventory of the reactor i coolant system include water level in the pressurizer. If the water level drops below the i lowest pressurizer level instrument reading (during a potential overcooling transient), l then the subcooling margin would be monitored until the pressurizer level returned on scale.

O 21 l

l

i l

l 4.3.4 Decay Heat Removal (Figure 4-4)

The decay heat removal function is accomplished by removing decay heat and stored heat from the reactor core and reactor coolant system at a rate such that overall reactor i

coolant system temperatures can be maintained at 532*F for hot standby condition. The

isolation of the secondary side of the steam generators and the use of the sixteen main

' steam safety valves will enable short term decay heat removal. While the reactor coolant l system is at high temperature, the steam generators can be used for removing decay heat j

" l from the reactor.

!- To remove decay heat via the steam generators, it is necessary to establish natural 4

circulation of reactor coolant between the core and the steam generators. Since the i reactor coolant pumps are unavailable due to the loss of offsite power, natural circulation l

normally requires the reactor coolant to be subcooled to minimize void formation within l the reactor vessel. After natural circulation is established, heat can be removed from l l

the reactor coolant system by boiling the feedwater on the secondary side of the steam l l generators. The steem generated from this boiling can be discharged to the atmosphere j through the main steam atmospheric steam dump valv'es (MSV-025 and MSV-026) to

! establish the long-term decay heat removal function. The decay heat removal function is made up of prerequisite conditions that include primary system reactivity, inventory and pressure control to maintain the RCS in a subcooled liquid condition, and secondary

side level and pressure control to provide for adequate heat transfer.

i

! A Two (2) atmospheric steam dump valves are available for decay heat removal. Both

!V valves are selected as the primary and backup trains for USI A-46. One steam generator t and one atmospheric steam dump valve are adequate for decay heat removal. Instrument j air is required for control of MSV-025 and MSV-026, and is supplied through the instrument air system. A backup supply of nitrogen is also available. The main steam L safety valves (MSSV) also can be used to discharge steam if the secondary side pressure L exceeds the MSSV set point. Make-up water can be fed into the secondary side of the l

! steam generators through the Emergency Feedwater System.

. Either the turbine driven emergency feed water (EFW) pump EFP-2 along with steam

inlet valves ASV-204 and ASV-005, and associated flow control valves EFV-55 or EFV- 1

! 56 or the motor driven EFW pump EFP-1 along associated flow control valves EFV-57 or EFV-58 may be used as the path for providing EFW to the Steam Generator, i The Emergency Feedwater Tank inventory, the Condensate Storage Tank inventory, and l the Condensate Hotwell inventory are u:;ed as the source of water for the EFW system j and are sufficient to maintain the plant at hot standby for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

i Process variables which are used for monitoring the decay heat removal function include j reactor coolant temperature and pressure. Both the reactor coolant hot leg temperature and the cold leg temperature can be measured during natural circulation decay heat L removal conditions to verify that natural circulation is established between the reactor core and steam generators.

22 s

L L 4.4 Electrical and Mechanical Support Systems for Hot standby 4.4.1 Emergency Diesel Generator Services 1

4 The emergency diesel generators are the alternative on-site power source. The auxiliary systems required to provide emergency services for the emergency diesel generators are the fuel oil, lube oil and jacket water cooling, starting air and room ventilation systems.

All mechanical components located near the diesel generators in the Diesel Generator Building are included as part of the diesel generators.

4.4.2 Electrical Power Distribution Since offsite power is assumed to be lost for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the safe shutdown capability must utilize on-site diesel generator power for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Hence, the electrical distribution system identified here to support safe shutdown components is essentially the engineered safeguard system. Review of plant procedures and evaluation of the electrical failure of an entire train are performed to determine capability to achieve the four safe shutdown functions.

The following electrical systems are required for achieving the safe shutdown functions:

A. 4160 Volt System G The 4160 volt system consists of five (5) switchgear buses. Only 4160 volt ES U Buses A and B are class 1E engineered safeguard switchgear and are required for shutdown.

B. On-site Diesel Generators Two diesel generators are provided for shutdown and are connected to the 4160V ES Buses. Each generator is rated at 3000 KW and has sufficient capacity to supply power to required safe shutdown components. Emergency Diesel Generators are on standby and will start automatically upon loss of 4KV power.

C. 480 Volt System The 480 volt system receives power from the 4160 volt system. T! e 480 volt ES buses comprise 2 redundant class 1E electrical systems and are required for shutdown. The 480 volt plant auxiliary bus is a non-lE bus fed from one of the 4160 volt ES buses.

This bus is can be cross tied to any of the other non-lE 480 volt buses except the 480 volt reactor auxiliary bus 3A. The 480 volt reactor auxiliary bus 3A can be fed from 480 ES bus 3A. Several of the motor control centers fed from both the lE and non-lE buses are required for shutdown operation using normal operating procedures.

Other electrical systems required for safe shutdown functions include:

The 250/125 volt DC system including:

23

- 8

i l Batteries - DPBA-1 A, DPBA-1B, and DPBA-1C, Chargers - DPBC-1 A through DPBC-11, and, 1

O Distribution panels - DPDP-1 A, -1B, -1C,

- DPDP-3A and DPDP-3B,

, - DPDP-4B,

" - DPDP-5A and DPDP-5B, j - DPDP-6A and DPDP-6B, and i - DPDP-8A through DPDP-8D; and j

The 120 volt vital power system including:

l Inverters - VBIT-1 A, -1B, -1C, -1D and IE, Distribution panels - VBDP-3 through VBDP-11, Regulating transformers - VBTR-2E, i - VBTR-3E, I - VBTR-4A through VBTR-4D, J Transfer switches - VBXS-1 A through -1E,

- VBXS-2A and VBXS-2B, and

- VBXS-3A through -3D; and l

! The 120 volt regulated power system including:

i Distribution panels - VBDP-1 and - 2, and i - VBDP-12 through -15, i Regulating transformers - VBTR-1 A and -1B, l

- VBTR-2E and VBTR-3A, and

- VBTR-4A through -4D; and The 120/208 volt AC power system including distribution panels -51, -51 and -

68, and associated transfonners.

i

! 4.4.3 Nuclear Service Closed Cycle Cooling Water (NSCCW)

One NSCCW cooling pump (SWP-1A or IB) is required for all modes of operation .

required for safe shutdown. One of the 4 NSCCW coolers (SWHE-1 A, IB,1C, or 1D) is required for normal NSCCW cooling system operation, but two are normally in service. NSCCW cooling pump SWP-1 A and coolers SWHE-1 A and IB are selected as the primary equipment for safe shutdown and pump SWP-1B and coolers SWHE-1C and ID are the backup equipment. The nuclear service sea water system, supplies cooling water to the NSCCW coolers.

For plant shutdown operations, this system provides cooling to: ,

! Letdown Coolers (MUHE-1 A, IB, & IC)

Reactor Building Fan Coolers (AHHE-31 A, B, & C)

Reactor Building Fan Motor Coolers (AHHE-32A, B, & C)

Reactor Coolant Pump Seal Area Coolers

/ Reactor Coolant Pump Motor Coolers (Upper Bearing Cooling, Lower Bearing Cooling, and Air Cooling - RCP-1A,1B,1C & ID) 24

Nuclear Service Closed Cycle Cooling Pump Motor Coolers (SWP-1A,1B, & IC)

Nuclear Service Sea Water Pump Motor Coolers (RWP-1, RWP-2A & 2B) l Reactor Coolant Pump Seal Return Coolers (MUHE-2A & 2B)

Makeup Pump 1B Motor Cooler (MUP-1B) -

Motor Driven Emergency Feedwater Pump Motor and Gear Oil Coolers (EFP-1)

Spent Fuel Coolers (SFHE-1 A & IB)

Spent Fuel Coolant Pumps Air Handling Units (AHHE-29A & 29B)  ;

Control Complex Chillers (CHHE-1 A & IB) I Instrument Air Compressors (IAP-1 A & IB) when the Secondary Service Closed l Cycle Cooling System is unavailable because offsite power has been lost.  ;

The system is required to operate during hot standby whenever the equipment it is cooling is in operation. 1 4.4.4 Nuclear Service and Decay Heat Sea Water The Nuclear Service and Decay Heat Seawater Systems are hydraulically separate systems. The Nuclear Service Seawater System cools the Nuclear Service Closed Cycle  ;

Cooling Water System and runs all the time. The Decay Heat Seawater System Cools  !

the Decay Heat Closed Cycle Cooling Water Systems (2 separate trains) and runs only l when one of those trains is running (mostly only when the Decay Heat Removal System l is in operation).

4.4.5 Decay Heat Closed Cycle Cooling Water This system provides cooling water to make-up purification pumps MUP-1 A and IC.

Make-up and purification pump, MUP-1B is in operation under normal plant conditions and is provided cooling water by the nuclear services closed cycle cooling water system.

If make-up pump MUP-1B is not available, the use of make-up pump MUP-1A or IC will require that the decay heat closed cycle cooling water system associated with the operating pump be in operation or the nuclear services closed cycle cooling water system valves be manually aligned to provide cooling from that system. The nuclear services closed cycle cooling water system can be aligned by manual valves to provide cooling for either the make-up pump MUP-1A or IC, which is then the normally operating pump. I l

4.4.6 Control Complex Ventilation i

The Control Complex Ventilation Cooling Units (AHHE-05A and 05B) are required for safe shutdown in order to maintain acceptable temperatures within the control room, switchgear, relay rooms, battery charger and battery rooms. These units include fans (AHF-17A, B and 19A, B), chillers (CHHE-1 A and IB) chilled water pumps (CHP-1 A and IB) and associated dampers.

25 i

I l 4.4.7 Emergency Feedwater Instrument Cabinet Room Coolers AHHE-43 & 44 are the Emergency Feedwater Initiation and Control (EFIC) System cabinet room coolers. Their heat sink is the Chilled Water System. They are required

! to maintain the EFIC electronics operable.

i

! '4.4.8 Diesel Generator Building Ventilation

Heating and Cooling for the emergency diesel generator (EDG) rooms are separate.

l Cooling is provided by one of two fans for each EDG. AHF-22A & B for EGDG-1A i and AHF-22C & D for EGDG-1B. The fans auto start when the EDG starts and stay off

otherwise.

1 The jacket coolant and lube oil for the EDG's are both heated so the EDG rooms never

get cold.

4.4.9 Instrument Air

! The Instrument Air System is on the SSEL. Power for IAP-1 A & IB comes from the 480 volt Reactor Auxiliary Buses which are non-1E, but they can be cross-tied to the ES Buses. Cooling for the compressors can be provided by either the Secondary Services Closed Cycle Cooling Water System (non-safety) or the Nuclear Services Closed Cycle

Cooling Water System. Procedures allow for operation of the instrument air compressors during a loss of off-site power.

.OD p In addition, the atmospheric dump valves (MSV-25 & 26) have nitrogen bottles which can be manually valved in to restore operation following a loss ofinstrument air. This could be used in the interim until the electrical and cooling water systems were realigned

to support operation of the Instrument Air System.

4.4.10 Reactor Building Ventilation .

The reactor building ventilation system consists of 3 fan assemblies; AHF-01 A/B/C and associated coolers AHHE-31 A/B/C which cool the containment air volume during normal operation as well as during emergency environmental conditions, should they occur.

Reactor building ventilation is required to maintain suitable and safe ambient conditions for operating equipment, and for instrumentation loops located inside the reactor building. The reactor building heat load is dissipated by the NSCCW System heat exchangers.

4.4.11 Lighting Requirements

a. Required Lighting There are no requirements for any permanent lighting. All required lighting supplement will be accomplished with flashlights and portable lights. Both battery powered and O _ plug-in units connected to a diesel backed outlet will be utilized.

26 i

I

b. Lighting Verified O

V The local battery powered light units were originally installed Seismic, anti falldown in l

Category 1 Structures. During the walkdowns these units were generically reviewed for l interaction concerns by the walkdown teams. The results of this review confirmed that the units would not fall down during an earthquake. Since the unit remains in place it should function as required after the event, providing additional ambient lighting for operations personnel.

4.4.12 Spent Fuel Cooling This system circulates spent fuel pool water through spent fuel coolers (SFHE-1A and IB) to remove the heat generated from irradiated spent fuel stored in the pools. Without cooling for spent fuel pools for an extended period of time, radiological release to the  :

environment could occur. Although control of radiological release as a result of a loss of spent fuel pool cooling is not required by PSP, FPC included the spent fuel pool j cooling system as a part of the seismic walkdown effort. l a 1 There are two main spent fuel coolant pumps (SFP-1A and IB) and two spent fuel coolers (SFHE-1 A and IB). Either of the spent fuel coolant pumps may combine with -

either of the spent fuel coolers to cool either spent fuel pool A or spent fuel pool B.

Both pumps and coolers will be used to remove decay heat from spent fuel stored in both pools, if required, and at the time of an entire core offload. During normal long term q storage of spent fuel in the fuel pools, only one train of the system components will be used to maintain the pools below 135'F. I V

4.5 Description of Safe Shutdown Equipment List

! The basic approach and format used for the Safe Shutdown Equipment List (SSEL) is similar to that described in the PSP. The following describes the information included I in each field in the SSEL. The general SSEL notes and SSEL line items notes are  !

described and included in Appendix B. l

! Entry Descriotion of Contents  !

. 1. SEQ No. This column contains a three-digit record number. This ,

identifies the table sequence number. The sequence I numbers are sequenced according to the time of entry into the table.

2. Train This column contains one of the following " train" numbers which serve to group components required to complete the path for the safe shutdown function.

I

1. Train 1: can be considered the primary train. Train

,p i equipment operates from Diesel Generator "A".  ;

V Required by the PSP.

27

W Train 2; can be considered the secondary, or 2.

p redundant train. Train 2 equipment operates from Diesel Generator "B". Required by the PSP.

i

3. Equipment Class This column contains a number between 0 and 21. The number corresponds to major equipment class, assigned in the PSP, Table 3-1 which corresponds to the equipment categories included in the seismic experience ,

data base. l 1

4. Equipment ID This column contains CR3 equipment identification number.

5. Description of This column contains a brief description of the Equipment equipment.

6. Drawing No. This column contains the piping or plant general arrangement drawing number (and sheet) which identifies the equipment location. ..

7. Building This column identifies the CR3 building where the equipment is located.

8. Floor Elevation This column contains the elevation of the building floor from which the equipment can be seen.

9. Eval. Type This field assists in manipulating the database. This field contains any one of the following 2 options. (N) - No seismic review needed. "S" - seismic review required to l

ensure seismic adequacy.

I

10. Notes This column may contain a number which identifies a note (applicable to the SSEL) found in Appendix B.

11. Normal State This entry identifies the normal state of the equipment during normal operation of the plant (e.g., open, closed, or o/c) for valves; run or off for pumps, etc.

12. Desired State This entry identifies the desired state of the equipment required for the safe shutdown function.

13. Power Reg'd The POWER RQD Field is used to document the need for electrical oower only and the supply source for that ,

power is documented in the REQ'D l INTERCONNECTIONS & SUPPORTING COMPONENTS column along with any other supporting 28

[

E 1

i

system such as Instrument Air (IA) or cooling water O (NSCCW, DHCCW, etc.).

• V l The power required field has been coded "YES" if power is required to move the components to the desired

position or maintain the component in the desired

! position. "NO" has been assigned to those components

! which are in their desired position and failin that desired j position or those components which have no electrical 1 mterface.

! 14. Supporting System This column contains the flow drawings or electrical

!- Drawing No./ Revision drawings which identify equipment or the operating and j control power sources.

15. Required Inter- This column includes the supporting equipment (by -

! connections and tag) or systems needed by the equipment described j Supporting Components in this database record to perform its safe shutdowri ,

function. Each supporting or associated component has a separate database record.

l The Composite SSEL is included in Appendix B. This list includes all of the equipmen't

identified as being needed for safe shutdown of the plant inchiding equipment which was

reviewed for seismic adequacy.

J 4.6 Operations Department Review of SSEL In accordance with the PSP guidelines, the Safe Shutdown Equipment List (SSEL) t generated for resolution of USI A-46 was reviewed for compatibility with plant j procedures for shutdown of the plant. The plant's Operations Department verified the compatibility of the SSEL with the plant's normal and emergency operating procedures.

l The purpose of this review was to verify that the operators, following existing plant procedures, will eventually be directed to the use of equipment and instruments on the SSEL even though the operator may have first tried to shut down using equipment not included in the SSEL. Several methods are suggested in PSP Section 3.7 for performing this review. FPC selected a " desk top" review of the flow drawings and applicable procedures to ensure that the plant can be brought to a hot standby condition following an earthquake and maintained there for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Plant Operations i representatives have verified that all equipment required in the operating and emergency

. procedures for the selected safe shutdown path are included on the SSEL.

i In the event of an earthquake, plant seismic annunciator alarms will be initiated in the l control room. Upon receiving a valid alarm, plant alarm and emergency procedures.

AR 303, " ESC Annunciator Response" and AP-961 " Earthquake" direct operators to

l. .

\

manually trip the reactor if the conditions for a reactor trip are met per reactor trip procedure EOP-2, " Vital System Status Verification". If the conditions for a reactor trip 29  !

1 1

i

are not met, the procedure directs the operators to verify all control rod and power  ;

\ distribution parameters are within limits. The procedure also provides general guidance l to determine overall impact of event on plant equipment. These procedures are adequate for plant response to the seismic event.

4.6.1 Conclusion of Operations Department Review I

FPC concludes that the equipment specified in the SSEL is sufficient to permit bringing the plant to a hot standby condition and maintaining it in that condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> using the methodology and requirements contained in the PSP. While some operator actions are required, adequate staffing, direction and time are available to accomplish the required actions. FPC also concludes that the current operation and emergency procedures contain adequate guidance to ensure that safe shutdown can be achieved and maintained if only the equipment on the SSEL is available following a SSE.

O t

1 t

J

\

Q 30 i f

I t

1 4

O 1

REACTOR REACTIVlW i CONTROL (PWR) a i

Initici ond Continued Control

! If CONTROL ROD 4

INSERBON i

Long-Terrn Control During Cooldown Of Reactor Coolont i

- u

(

. U u MU INJECTION HPI INJECTION OF OF

! BORATED WATER BORATED WATER i

if If d

4

' (~ .

Figure 4-1: Safe Shutdown Alternatives for Reactor Reactivity Control

. 31 i

4

4 1-i

!O REACTOR COOLANT PRESSURE CC'NTROL (PWR) i 1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i b l 2

1 Decrease Pressure i i

Y .u u y i

j' ,

PRESSURIZER PRESSURIZER PRESSURIZER DHR SRV l

, SRV O!SCHG. DISCHARGE PORV AUXIUARY

! (Al SRV Set Point DISCHARGE SPRAY (At SRV Set Point ressure Only) Pressure Only)

]

o o u y 1.

Increase Pressure i i U i If if if If MAKE-UP AND HPl PRESSURIZER LPl FEED PURIFICATION FEED HEATERS (Low Press. Only)

SYSTEM i

e f 1f N i

i' .

4 i

Figure 4-2: Safe Shutdown Alternatives for Reactor Coolant Pressure Control 32 1 -

f

4 W

i.

I i

i i

{

REACTOR dOOLANT

_ INVENTORY CONTROL (PWR) l Feed into System *

}~

y f l' jr 1 .MU HPl LPl FEED j FEED FEED (L w Press.

q Only)

}

F U p 4

V _ -

Items To Control To Minimize Discharge From System n

( F o

!' o

). REACTOR COOLANT PRESSURIZER OTHER j

PUMP SEAL PORV i VENTS AND LEAKOFF DISCHARGE DRAINS i

o n

1 j NORMAL AND PRESSURIZER EXCESS LETDOWN SRV DISCHG.

PATHS (At SRV Set Point

, Pressure Only) f 4

jr ,

Figure 4-3: Safe Shutdown Alternatives for Reactor Control Inventory Control l

33

/

r.

O DEC AY HEAT REMOVAL (PWR).

High Pressure Operation Steam Generator Cooling 9

k &

MAIN STEAM MAIN STEAW ATW. STEAM SRV DISCHARGE DUMP valve (" 5W stT Po#8T OtSCHARGE "" M t 6 o

EMERGJEEDWATER FEED TO STEAu cEN.

Low Pressure Operation 4

6

! DECAY HEAT j REMOVAL SYSTEM .

4

. i DECAY HEAT CLOSED l

CYCLE COOLING WATER I

i 1r l

NUCLEAR SERVICES AND 1 DECAY HEAT SEAWATER 1

it i t i

l i

Figure 4-4: Safe Shutdown Alternatives for Decay Heat Removal ls 34 i

t f

l l

5. ' Mechanical and Electrical Equipment Review 5.1 Summary of Review The seismic screening and walkdown included verification of 727 equipment items in the 20 classes of equipment and the "other" equipment class.

i The review of the seismic adequacy of mechanical and electrical equipment on the i Crystal River Unit 3 Safe Shutdown Equipment List was performed in accordance with Section 4 of the PSP (Reference 2). SEWS forms in conformance with the PSP were used to record the screening and walkdown results. All data was recorded in a common database with the SSEL.  :

i i Thirty five (35) items, including 12 tanks, could not be walked down due to )

inaccessibility. A listing of those items and their status is provided in Table 5-5.

The results of the screening and walkdown are presented in the Screening Verification 4

Data Sheet (SVDS) forms included in Appendix C. 1 5.1.1 Seismic Capacity vs. Demand l i

With the exception of six items of equipment, the Crystal River Unit 3 in-structure response spectrum for all SSEL items is enveloped by the SQUG Reference Spectrum:

The six items of equipment that have in-structure response spectra (calculated by Biggs method) that exceed the SQUG Reference Spectrum are the following:

i Item Class Building Elevation SF-9-FIT 18 Auxiliary 143' AH-967-SV 8B Auxiliary 160' AH-196-POS 10 Auxiliary 160' AHD-01D 10 Auxiliary 160' RCV-10 8B Reactor 168' RCV-11 . 8A Reactor 168' With the exception of the six items identified above, all items of SSEL equipment for Crystal River Unit 3 meet the PSP (and SQUG GIP) capacity / demand requirements.

These six items are classified as Outliers.

i 35

d

. 5.1.2 Equipment Class Descriptions The distribution of the equipment items in each equipment class is shown in Table 5-6.

s 5.1.3 Equipment Anchorages The majority of floor mounted mechanical and electrical equipment is mounted on reinforced concrete pads. All reinforced concrete pads are integrally attached to the concrete floors by dowels. Some floor mounted equipment is bolted directly to structural

. steel frames.

l The floor mounted electrical enclosures typically have a base which is bolted or welded to the enclosure. For concrete floors the base is anchored either by expansion anchors or by welding to embeds in the concrete pad. For steel floors the base is welded or bolted.

2 The majority of wall and ceiling mounted mechanical and electrical equipment is mounted either by expansion anchors or by use of bolting to Unistrut embeds in the wall.

Where practical, anchor bolts were tightness tested by hand to assure that they did not freely spin in place. No such instance was found.

5.1.4 Seismic Interaction Crystal River Unit 3 exhibits good practice in housekeeping. Maintenance and Operations equipment is generally either stored remote from safety related eaiiioment or is secured to preclude interaction. As a consequence, very few housekeeping < action issues were identified in the walkdown.

l!

. Due to the low seismic nature of the plant and the generally stiff supporting of

distribution systems, proximity interactions due to relative motions of supported items are rare.

A number of cabinets (containing relays) were found which were not bolted to adjacent cabinets.

In the turbine building, the major issue identified is potentially weak block walls in proximity to a number of (non-safety related) SSEL items.

i The conclusion of the SRTs is that CR3 design, maintenance, and operations practices

along with the low seismic nature of the site result in good design for seismic interaction.

5.2 Instances of Intent but Not Letter of PSP Caveat Met Other than the tanks and heat exchangers identified in Table 5-3, there were no instances of intent but not letter of PSP caveat met for electrical or mechanical equipment.

36 7

5.3 Summary of Outliers The following general types of outliers were found.

Capacity:

• In-structure demand exceeds screening capacity Caveats:

o Potentially weak construction of battery racks e Potential need to provide lateral support for transformers l

e Vibration isolators without lateral support e Maintenance issues - items not correctly reinstalled following maintenance (missing mounting bolts and control room ceiling hardware) e Vertical pump shafts exceeding 20' e Relays missing wire restraint clip e Battery rack rails not snugly fit to batteries Anchorage:

e Unanchored (or poorly anchored) cabinets (all unanchored cabinets are not safety-1 related items on the SSEL) p e Unanchored transformers (all unanchored transformers are not safety-related items

~! on the SSEL) e Potential need for additional tubing supports (or repair) e Anchorage design data (drawings and/or calculations) not yet located 7

Interaction 1

e Potentially weak block walls in the turbine building l e Cabinets with relays not bolted together e Maintenance items left in close proximity to cabinets with relays (this was extremely rare - in general, all maintenance items were secured to preclude impact with other equipment) e Potential proximity interaction with permanent maintenance and operations equipment

, e Unrestrained breaker trolleys e Missing door latch on relay panel e Potential interactions of piping components with structural members A listing of outliers and resolutions is provided in Table 5-4.

No items were found to have Design Basis Deficiencies.

37

Table 5-1 Response Spectrum Exceedances for Building Elevations O Structure Elevation Frequency Range Where IRS Exceeds ABS Reactor Building 160' and higher 9 Hz Auxiliary Building 143' and higher 11 to 18 Hz Control Complex Nonem N/A Emergency Diesel Nonem N/A Generator Building Intermediate Building Nonem N/A Emergency Feedwater Tank Nonem N/A Enclosure Turbine Building Nonem N/A

• All SSEL items are located at elevations below 40' above grade.

O I e

l t

2 O

38

. . .-. . .-- . . - - - - - - - - - - - . .=

. - . . - . - _ - . . - - . . - . - - . - . - . . . _ _ . . - . . . . . - . . . . . . ~ - . . . . . . _

i Table 5-2 Effective Grade for Plant Structures

'O l Structure " Effective Grade" (Elev., Ft.) ,

Reactor Building 95'  !

Auxiliary Building 95' Control Complex 95' Emergency Diesel Generator Building 119' Intermediate Building 119' Emergency Feedwater Tank Enclosure 118.5' Turbine Building 95' O

39 1

O  %

TABLE 5-3: Equipsnent Intent But Not Letter of Caveat Summary 18-Dec-95 -

SEQUENCE CLASS ID NO BUILDING ELEV INTENT 134 21 CAT-5A AUXILIARY I19 (*) The longstudinal frequency for honzontal tanks per the GIP is haed on the =====phan that the saddle plate and its stiffeners bend with a fixed connection at the tank and a -

pinned connection at the base plate. Per this sneehad the

~

calculated longitudinal L %af s 26 i Hz and the tank is considered "flexsble". Homer, this tank is well braced longitudinally with two cross members connecting the top and bottom extremes of each saddle (cross bracing exists on both sides of the tank) Therefore the bending stiffness of the i saddles is significantly greater than calculated and the resulting longitudinal L+ cy is underesta==ned The actual tank longitudmal frequency is greater than 33 Hz and the tank was therefore assunned " rigid" longitudinally.

144 21 CAT-5B AUXILIARY I19 (*) The longitudinal frequency for horizontal tanks per the GIP 4 is based on the -_ ,c_+ that the saddle plate and its o

stiffeners bend with a fixed connection at the tank and a pinned connection at the base plate. Per this method the calculated longitudinal f.yaf s 26 i Hz and the tank is considered " flexible". However, this tank is well braced longitudinally with two cross members connecting the top and bottom extremes of each saddle (cross bracing exists on both sides of the tank). Therefore the bendicg stiffness of the saddles is significantly greater than calculated and the i l

l resulting longitudinal frequency is underestimated. The l actual tank longitudinal frequency is greater than 33 Hz and I the tank was therefore assumed " rigid" longitudinally.

l j .

Table 5-3

1. . _

.-. - ~~ - . - an. . . - .

7.. - - --

s O O SEQUENCE CLASS IDNO BUILDING ELEV INTENT AUXILIARY 095 Table 74 of Secison 7 of FPC's Plant Spec Ge Procedure for 45 21 DCHE-lA r-dimenam of the USI-AM issue speci6cs that the applicable range of sadde spacing for horizontal tanks and heat exchangers is 3* <

S < 27. This heat exchanger has 22* spacing. However, the heat a '- y is rigid longitudinally, the cairmt=amn resuks very only shghtly versus the same heat exchange with 20' saddle specsag, the capacity >> demand, and the heat M- ; r is located at the base elevanson in a low seismic area. It is concluded that the insent of the caveat is unet and the anchorage calculamon is appbcable.

AUXILIARY 095 Tabic 74 of Section 7 of FPC's Plant Spec Sc Procedust for 64 21 DCHE-1B resolutsam of the USI-AM issue specifies that the appiscable range of sadde spacing fer hori== sal ankst and heat exchangers is 3* <

S < 20'. This heat exchanger has 22* spacing. However, the heat exchanger is rigid longitudinally, the calaal=eion resides vary only slightly versus the same heat exchange with 20* saddle spacing.

the riparney >> demand, and the heat exchanger is located at the 4^ base elevation in a low seismic area. It is concluded that the intent of the caveat is met and the anchorage calculation is applicable.

AUXILIARY 095 Table 74 of Section 7 of FPC's Plant Specinc Premtisse for 108 2I SWHE-lA resolution of the USI-AM issue specifies that the apphcable range of saddle spacing for hornental tanks and heat #- ,, -s is 3' <

S < 20'. This heat exchanger has 22' spacing. However, the heat exchanger is ngid longitudinally, the calculation results vary only slightly versus the same heat exchange with 20* saddle spacing, the capacity >> demand, and the heat exchanger is located at the base elevation in a low seismic area. It is concluded that the intent of the caveat is met and the anchorage calculation is applicable.

Table 5-3 m - _

_ _ _ _ _ _ _ _. __ . _ _ _ . _ _ _ _ _ . . . _ _ _ . . _ _-. .__.m__ . . .. . _ _ . _ _ . _ _ .

1

SEQUENCE CLASS IDNO BUILDING ELEV INTENT 109 21 SWHE-1B AUX 1LIARY 095 Table 74 of hesia= 7 of FPC's Plant WAc Procedure for re= alma a= of the USI-AM issue speranee that the apphcable range of saddle spacing for horizontal tanks and heat +- ' 1 -. is 3' <

I S < 20'. His heat exchanger has 22' spacing However, the heat euch==ger is rigid !=g ",, the c= ands a= resuhs vary only slightly versus the same heat exchange with 20'sadde spacag, the capacity >> desmand, and the heat euchnager is located at the base elevanan in a low semanac area. It is concluded that the l -

intent of the caveat is met and the anchorage c*=8=saam is  ;

110 21 SWHE-lC AUXILIARY 095 Table 74 of Section 7 of FPC's Plant Specific Proadure for resolution of the USI-AM issue specifies that the apphcable range .

of saddle spacing for honzental tanks and heat exchangers is 3' <

S < 20'. This heat exchanger has 22' spacing. However, the heat  !

- ' ; r is rigid longitudinally, the calculauon resuks vary only t slightly versus the same heat exchange with 20' saddle spacing. [

the capacity >> demand, and the heat < schanger is lacased at the ~

base elevanon in a low scismic area. It is concluded that the i M intent of the caveat is met and the ==charage calculanon is +

appl e l t

1II 21 SWHE-1D AUXILIARY 095 Table 74 of Secuon 7 of FPC's Plant Specific Procedure for resolution of the USI-AM issue specifies that the apphcable range of <=ddle spacing for hornaasal tanks and beat cych*aters is 3' < t S < 20'. This heat evchanger has 22' spacing. However, the heat l 1 exchanger is rigid longitudinally, the calculataca re<=h< vasy only slightly versus the same heat exchange with 20' saddle spacing, i the capacity >> demand, and the heat exchanger is located at the base elevation in a low seismic area. It is concluded that the j intent of the caveat is met and the ancharage c*=Insaan is applicable.

Table 5-3 m __ . _ _

7 l 0 Cp U 1

l l TABLE 5-4: Equipment Outlier Description and Resolution Summary 18-Dec-95 SEQ ID NUMBER BUILDING ELEV OUTLIER DESCRIPTION OUTLIER RESOLUTION 469 ACDP-68-T CONTROL 124 Transformer coil not supported Modification: Prmide longitudinal support for j longitudinally. the coils.

l f 720 AH-l%-POSI COKIROL 160 Capacity "N" The in-structure response Review amplitudes ofin-structure response l

spectra for this elevation exceeds the SQUG spectra and determine if there are available test

! Reference Spectrum. reports.

Bounding Spectrum #6: Tubing attached to Modification: Add supports for tubing.

positioner is not supported.

721 AH-l%POS2 CONIROL 108 Bounding Spectrum #6: Tubing from the Maintenance: Repair support.

positioner has a broken support (second support from positioner) which leaves the tubing unsupported over a long length.

g 722 AH-l%POS3 CONTROL 164 Bounding Spectmm #6: Tubing from Maintenance: Secure tubing.

positioner is tie-wrapped to ist support. It is very loose and moves freely.

263 AH-%7-SV AUXILIARY 160 Capacity: The in-structure response spectra Review applicability of GERS for solenoid for this elevation exceeds the SQUG valves.

Reference Spectmm.

237 AHD-01D AUXILIARY 160 Capacity: The in-structure response spectra Resiew amplitudes ofin-structure response for this elevation exceeds the SQUG spectra and determine if there are available test Reference Spectrum. reports.

256 AHF-17A CONTP.0L 164 Anchorage 1: Fan has isolation type (a) Perform calculation to determine anchorage supports that do not appear to be adequate adequacy or (b) modify anchorage to include for lateral loads. lateral restraint (bumpers).

264 AHF-17B CONTROL 164 Anchorage 1: Fan has isolation type (a) Perform calculation to determine anchorage supports that do not appear to be adequate adequacy or (b) modify anchorage to include for lateralloads. lateral restraint (bumpers).

279 AHP-01 A CONTROL 164 Anchor Bolts and Embedment: Verify that Perform search for applicable drawings.

pad is reinforced.

Table 5-4

. _ ~ . _ . . _ , _ _ . . _ . . . _ _m .. ..

s

[~ v  ;

l l

SEQ ID NUMBER BUILDING ELEY OUTLIER DESCItFTION OUTUER RESOLUTION 280 AHP-OlB CONIROL 164 Anchor Boks and Fmhedmarna Verify that Perfona search for applicable drawings.

l: pad is resaforced.

l l 281 AHP-01C ' CONIROL 164 A= char Boks and F=dwdanema Verify that Perfona search for apphcable drawings.

pad is scanforced.

282 AHP-01D CONHtOL 164 Anchor Bolts and Famhedament- Venfy that Perfona scarch for apphcable drawnags.

'. Pad is reaaforced.

601 ATCP-1. CONTROL 124 laseractaon #5: SOLA UPS (tag AN) os hen se===ne- saamas ernad bok. ,

t second shelf front bottosa is secure with only I bolt. t l- 129 CAP-1B AUXILIARY I19 Anchorage 1: One bolt missing from niotor Performa cair= Ins == to detenname nacharage support to anosor base. adequacy i

l

+ -

l b.

I Table 5-4 m - _ __- _ ___ ____ _ _ - _____ _ _ _ _ - - - _ - - _ _ _ _ _ _ _ _ - _ - _ _ _ _ - - ._ -. . - _ -. _.

/-

SEQ ID NUMBER BUILDING ELEV OUTLIER DESCRIPTION OUTLIER BESOLUTION 886 CEILING COfflROL 145 Review of CR3 MCR Ce hag for A46 as ' (a) Perforsa i==edsmana= desaga review to interactica source foren=srolRoomt desenname if the i=sended >=samlina== methods C=hament on SSEL. would be ve===c=Hy adequate, and (b) =====ae===nr to insedi ceihag as intended if-

1. Lights. - Ataq==nely supponed where . this is desennised ac % se===cnily adequase or strap goes under support and provides install namedic=*aan to assure sessmuc adagancy.

restraint However, strap goes front one light to the next one, so the strap is not effecove at the end o( or at a gap in, a run of lights. In addition, many m==artaa== cf light suppo ts to main imemahers are not correctly namedied (cads of synag leaded wire clips are not engaged in holes). Las for light is not posainely secured.

2. Main Strw Members. - Mais meinbers are spliced every 4 feet. .'Ihejoint is such that axial loads on the unemihers (axial loads 4 do occur in carthquakes - especially for os ceilings not laterally braced like CR3) will likely break thejoint. This will not cause the main member to fall, but it could tih and cause ceiling pancis and lights to fall.

3. W y StrW members. -The, secondary strut members are gravity supported only - at the splice discussed above. Even if the splice does not break, the secondary members are likely to fall - which will hkely cause ceiling panels and lights to fall.

i 74 DCP-1B AUXILIARY 095 Bounding Spectrust #7: A long run of Review the piping cdcuantana piping eed to this pump has an axial support which uses a pipe clamp without any axial lugs that could be visually confinned.

Table 5-4 M._._.._____._.___m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ __

i l

l 0 O f

SEQ ID NUMBER BUILDING ELEV OUTLIER DESCRIFTION OUTLIER RESOLUTION 198 DPBA-IA CONTROL 108 Bounding Spectrum #3: Confirmation that Review original msmic calculauon for the the weight is less than 450 h is required. racks to confirst weight < 450lb and to detennine if they would meet PSP requirements.

Bounding Spectrum #5: These a:e instraces where a 3/8" gap exists between the battenes Refit the rails to close gap as required.

and the rails at the front of the rack.

Bounding Spectrum #10: Rack construction appears to have weak connechon in virtually alljoints.

202 DPBA-1B COfGROL 108 Bounding Spectrum #3: Confirm. tion that Review original seismic calculation for the the weight is less than 450 lb is required. racks to confirm weight < 450lb and to deternune if they would meet PSP requiremenk Bounding Spectrum #5: There are instances where a 3/8" gap exists between the batteries Refit the rails to close gap as required.

and the rails at the front of the rack.

A CD Boundmg Spectrum #10: Rack construction appears to have weak connecuon in virtually alljoints.

434 DPBA-IC TURBINE 095 Interaction # 1: Block wall at one end of both Perform calculation of block wall adequacy.

racks & along one side of DPBA-1C.

435 DPBC-lG URBINE 095 Interaction #1: Block wall behind cabinet Perform calculation of block w2tl adequacy.

(6" away) should be checked 436 DPBC-1H TURBINE 095 Interaction #1: Block wall behind cabinet Perform calculauon of block wall adequacy.

(6" away) should be checked 437 DPBC-Il TURBINE 095 Interaction #I: Block wall behind cabinet Perform calculation of block wall adequacy.

(6" away) should be checked.

493 DPDP-IC TURBINE 095 Interaction #4: Block wall room. Perform calculation of block wall adequacy.

736 DPDS-IC TURBINE 095 Interaction #1: Block wall behind the Perform calculation of block wall adeqt ex/.

cabinet.

737 DPXS-IC TURBINE 095 Boundmg Spectrum #5 & Anchorage #2: Perform calculation of block w211 adequacy.

Mounted on block wall.

Table 5-4

..m._.. . . _ _ _ _ _ . _ . _ . ~. . . . . - . _ ._ . . . . _ . _ _ . _ . _ . _ . . . _ ._. _ _ . _ - - - - _

n BUILDING ELEV OUTLIER DESCRIPTION OUTLIER RESOLU110N SEQ ID NUMBER l

CONTROL 124 Inscracten #5: CRD Semce Power Supply ha===se===nr Mark storage area for CRD i 587 DRRD-2-1 on roller adpacent to DRRD-2-1. Semcc Power Supply away froma safety related i

l almpment.

l

559 EGCP-2A DIFSFL 119 Inscraction #2

Hear-here calmnet can Modification. (a) Move hear-here cdianes (b) i isnpact wall of panel, add soR spacer between hear-here cabinet and panel, or (c) brace hear-here cabinet so that it

. will not anove.

~

DIFSFI . 119 lateraction #2: Hear-here calmnet can Modifie=sian (a) Move hear-here calmnet,(b) 562 EGCP-2B inapact wall of panel. add soR spacer between hear 4ere ed==re and panel, or (c) brace hear-here cabinet so that it will not nuove.

313 EGDG-1B DIESEL 119 Inser=<1aan #2: Relay Cabinet has zero Modification. Drill hole in bracket at larmanan clearance with bracket on EDG on right side. of relay cabinbet interference to een====ne potential inser=<1=ait.

.p. 652 ERI CONIROL I45 Bounding Spectnam #7/ Anchorage #1: ERI (a) Perform calculation to determine 4 not anchored. overturning / sliding potential and (b) for c= acid =ned overturning / sliding paae=ss=8 inseractions, == char the apphcable cabanes(s).

653 ER2 CONTROL 145 Bounding Spectrum #7/ Anchorage #1: ER2 (a) Perform calculation to descraine not anchored. overturning / sliding potential and (b) for calculased overturning / sliding paseass=8 interactions, anchor the apphcable cabinct(s).

654 ER3 CONTROL I45 Bounding Spectrum #7/ Anchorage #1: ER3 (a) Perform calculation to determine not anchored. overturning / sliding potential and (b) for calculated overturning / sliding panensial inseractions, anchor the apphcable cabines(s).

655 ER4 CONTROL 145 Bounding Spectrum #7/ Anchorage #1: ER4 (a) Perform calculation to descrinane not anchored. overturning / sliding potential and (b) for calculated overturning / sliding panemaial interactions, anchor the applicable c=hanes(s).

Table 5-4

7 4

SEQ ID NUMBER BUILDING ELEV OUTLIER DESCRIFTION OUTLIER RESOLUTION 656 ERS CONTROL 145 Ranarhng Spectnam #7/Aachorage #1: ERS (a) Perform c=hiana= to desernisme not anchored. overturmang/rladiatr e 1

• and (b) for r=lculaaed ma ';/shding pane s.

inscrar1aans anchor the appbcable cabesce(s).

657 ER6 CONULOL 145 Bounding Spectrum 67/Aachorage #1: ER6 (a) Perform c=hinanaa to desenaane '

not nachared- owr ";! '; posentaal and (b) for calculated overt - ;!_;peacessal

- saferarenanc., anchor the applicable r=ha=ce(s).

658 ER7 CONIROL 145 Boundmg Spectrum #7/ Anchorage #1: ER7 (a) Perform calculation so desenmaac not anchared. overturning /shdaag pase=ani and (b) for cnicuissa,aa aun ';!shding; 4 -'

taaerartianc, anchar the apphcable cabeact(s).

659 ERS CONIROL 145 Bounding Spectrum #7/ Anchorage #1: ERS (a) Perform calculation so desennine not avhared. overturning /slidsag paseass=1 and (b) for c=icains,veovertunung/ sliding paae=*==

4 maecractanas anchor the appbcable enhanes(s).

Co

?

669 ESCP-4A CONTROL 145 lateraction #2: Tool box, storage cabinet, Madafirmanaa. Anchor pennanent cabiects. i flammable liquid cabinet about 30" away.

670 ESCP-4B COlGROL 145 Interaction #2: Tool box, storage cabinet, Modific=saa= Aachar per==neas cabinets.  ;

ii====hae liquid cabinet shaus 30" away.

671 ESCP-4C COKfROL 145 Interaction #2: Tool box, storage cabinet, Modafacation Anchor per==nent cabinets.

II====hle liquid cabiact about 30" away. .

i 672 ESCP-4D CONTROL I45 Imeraction #2: Tool box, storage cabinet, Modification Anchor per==near cabinets.

flammable liquid cabinet about 30" away.

673 ESCP-5A CONIROL I45 Interaction #2: Relay mounting panel Mainten= ace: lastall missing lasch.

missing lower latch.

426 IAP-1 A 'IURBINE 095 Interaction #1: Fan belt guard not anchored Maintenance: Reanchor the fan belt guard.

at motor end.

685 ICS-5 CONTROL I45 Bounding Spectrum #3: Cabanets are not Modification Attach cabinets ICS-5 and NNI-I connected. at top.

Table 5-4

SEQ ID MUMDER BUILDING ELEV OtfI' LIER DESCRIPTION OUTLIER RESOLUTION 354 MSV-411 INTER 119 laserarsiam 1: Air line in casuar* with fire Modificatson:(a) remove L- ' ;in the proofing. _ area of the air line, (b) support the air line so that it c===as anseract with the Lm _ '- ; or

(c) rerouse the air line.

570 MIMC-09 DftER 119 Anchorage #1: MCC on 4" high frame. Madifirmanam Camacca MCC to frasac Frame bohed to floor. MCC mot anchoral to (sam ==e=d by weldsag) franne.

576 MIMC-12 ~IURBINE 119 Banading Spectrum #7/Aachorage #1: Modafu:atsomt !=<sali ch===el clamps rather Ch==nel base is poorly == chared. than washers.

513 MTSW-2C CONTROL 108 laseraction #2: ('a=duit has 0" clearance Modefecataca Aranch enadma to cabsact or add with transformer enhn=ct soR spacer betwa:a conduet and cabanet.

516 MTSW-2F CONTROL 108 lateraction #2: Unastrut has 0* clearana on Modific=4=a=: Cut 1/2" off of Unastrut.

top of cabanet.

A 495 MTSW-3A 'IURBINE 095 Anchorage #1: The transformer hay for Modification: (a) Attach transformer to frasne

• MTSW-3A was not opened, but it is acammed (rema=ne=d bolting through slupping bolt that the samme outliers found in MTSW-3C holes) and (b) attach frasac to floor would apply to MTSW-3A. The transfonner (remaune=d weldsag the a=sade of the franse sits on a structural frame, however, (1) the to e=hed).

transfonner is not anchored to the frame and (2) the frame is not markved directly to the floor.

896 MTSW-3C TURBINE 095 Aachar=y #1: The transformer sits K a Modification: (a) Attach transfonner to frame structural frame, however,(1) the (recoaurend bolting through shapping bolt transformer is not anchored to the fr _see and holes) and (b) attach fraane to floor (2) the frame is not anchored M.Jy to the (recon ==e=d welding the a=sade of the frame floor. to embed).

497 MTSW-3D IURBINE 095 Anchorage #1: The transformer hay for Modification: (a) Attach transfonner to frame MTSW-3D was not opeacd, but it is =<aamed (recomunced boknag through shipping bok that the same outliers found in MTSW-3C holes) and (b) attach fraane to floor 8 would apply to MTSW-3D. The transformer (reca==ead weldsag the an=<=le of the frame sits on a structural frame, however, (1) the to embed).

transformer is not == chared to the frame and (2) the fran.e is not anchored directly to the floor.

Table 5-4

. _ _ - __ _ _ . _ . . . _ _ _ _ _ _ _ - . _ . _ . _ -_._ ._ -_.~_-.-.m_.. _ ____m_._ _. _ _ _ _ _ . .

m O

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SEQ ID MUMBER BUILDING ELEV OU11 nra DESCRAFTION OUTE1FR RESOLUTION l

l 602 MTSW-3F CONIROL 124 hi=dmar Spectrum #4: E:e trolley not Madaricasian lastall clamps to secure treuey in i l two du rena== (y,- '

'- to and parauct to restrained (on top ofc=hi=es).

the swischgear hacup).

i 603 MfSW-3F-T CONTROL 124 P-- =' ; Spectrum #4: No top bracing Modifirmanan Prmide top bracing for the ede=siriad transionner cons.

I 604 MfSW-3G - CONTROL 124 Bauading Spectrum #4: Troucy on top of Modifiemiaa t===Is lamps c so secure tsoucy in

. SWGR free to unwe longitudi==lly along its two darers- (m7-- ""-- to and pernas,ano  !

rails. the swuchgear hacup).

605 MTSW-3G-T CONIROL 124 handing Spectrum #4: No top restranat Modsficasian Preside top bracnag for the

< idensirmed. transionner coils.

498 MTSW-3J TURBINE 095 handing Spectnam #7 and Anchorage #1: Resiew fa==d=saan pad scanferre== ear Need to verify base is anchored or pad is resaforced.

095 Aachge #1: The transformer sits on a  !

ui 499 MTSW-3J-T TURBINE Modafication: (a) Attach transioneer so framme O structural frame, however,(1) the (reca=une=d boking through sluppsag bolt .

transfonaer is not anchored to the frame and haics) and (b) =n=ch framac to Soor (2) the frame is not == chared directly to the (maie=d weldian the aus<ide of the frame floor. to embed).

7 MUP-1A AUXILIARY 095 laternesian 4: U-tmit aussang in pipe over Madiricanan- lastall U-bolt.

motor -

152 MUV-051 AUXILIARY I19 lateracason #1: Possibic interaction hermine Resisit during outage to perfona tug test.

operator body 2" away from electncal box.

i 189 MUV-200 AUXILIARY 124 lateractaca Effects #1: Zero clearance Modafication: Cut steel plate to allow between sseet plane on operator and sacel minimussa 1" clearance with angic.

angle on wall.

704 Ni&P-D2 CONIROL 145 Interaction #2: Music Stand 24" from Replace aussic cand with a stable stand (i.e., a cabinet. stand with a low center of gravity) that can be used by operations without ca=cern for 8 overturning.

709 NNI-5 CORTROL I45 Boundmg Spectrum #3: Cabinets not bolted Modification: Attach cabinets ICS-5 and NNI-I together. at top.

i Table S-4

D v' SEQ ID NUMBER BUILDING ELEV OUTLIER DESCRIPTION OUTLIER RESOLUTION 710 NNI-6 CONIROL 145 Bounding Spectrum #3: Not bolted to Modification: Attach cabinets NN1-5 and NNI-cabinet NNI-5 (is boiled to cabinet NNI-7). 6 at top.

532 PORV/IEMP CONTROL 138 Bounding Spectrum #4: Apple IC keyboard Modancauon Secure keyboard.

not secured.

765 RCV-10 REACTOR 168 Capacity: The in-structure response spectra Review applicability of GERS for =lemand for this elevauon cur-k he t SQUG nives.

. Reference Spectrum.

648 RCV-11 REACTOR 168 Capacity: The in-structure response spectra Review applicability of GERS for motor for this elevauon exceeds the SQUG operased vahts.

Reference Spectrum.

714 RFL MPLXR CONTROL 145 Bounding Spectrum #3: RFL MPLXR not Modincation: (a) Bolt together or (b) add connected to adjacent GE rack. spacer between RFL MPLXR and adjacent rack.

634 RR2B CONIROL 124 lateraction #5: Door does not latch at the Maintenance: Correct latch problem.

cn top. Concern is potential banging effect on the relays.

535 RSA CONTROL 108 Interaction #2: Zero clearance between Modification: Add spacer cabinet and raceway fireproofing. Cabinet anchored with 6 3/4" diameter bolts.

536 RSA-1 CONIROL 108 Interaction #2: Zero clearance between Modification: Add spacer cabinet and insulation on wall. I/4" .

clearance between cabinet and bolt on w211.

98 RWP-1 AUXILIARY 095 Bounding Spectrum #2: Drawing FD- Perform calculation to determine acceptability 290493X shows the casing /shaA to of the casing / shaft cantilever about 28', which exceeds the 20' guideline.

90 RWP-2A AUXILIARY 095 Boundmg Spectrum #2: Drawing FD- Perform calculation to determine acceptability 290493X shows the casing / shaft to of the casing / shaft.

cantilever about 28', which exceeds the 20' guideline.

Table 5-4 m - -.

N1/

SEQ ID NUMBER BUILDING ELEV OUTLIER DESCRIPTION OUTLIER RESOLUTION 99 RWP-2B AUXILIARY 095 Bounding Spectrum #1: Drawing FD- Pt form calculation to detennene 9_- , " * 'i 290493X shows the renme/shaR to of the casing /shaR.

cantilever about 28*, which errwwk the 20' gudeline.

91 RWP-3A AUXILIARY 095 Bounding Spectrum #2: Drawing FD- Perform calculation to detenanne ---- , - ' "i 290493X shows the casing / shat to of the casang/shaR.

cantilever about 28*, which eurwek the 20' gudeline.

100 RWP-3B AUXILIARY 095 Bounding Spectrum #2: Drawing FD- Perform calculation to determane 3rrvps=h=Iny 290493X shows the r.asing/shaR to of the casang/shaR.

cantilever about 28*, which eurwek the 20' guedeline.

193 SF-9-FIT AUXILIARY 143 Capacity: The in-structure response spectra Resiew amplitudes ofin-structure response for this elevation exceeds the SQUG spectra and determine if there are available test Reference Spectrum reports.

us

" 97 SWP-1B AUXILIARY 095 Interaction 1: Small glass oil reservoir does Maintenance Replace protectiw wire cage.

not have protective wire cage. Fknarecerne light might fall and hit it.

84 SWV-354-SV1 AUXILIARY 095 Bounding Spectrum #3: Unistrut near SWV- Modafication: Positively attach Unistrut.

354-SVI and tubing not positively connected.

85 SWV-354-SV2 AUXILIARY 095 Bounding Spectrum #3: Unistrut near SWV- Modification: Positively attach Unistrut.

354-SV2 and tubing not positively connected.

607 TPC CONTROL 124 Anchorage #1 (and Boundmg Spectrum #7): Perform calculation to deternune adequacy of Missing anchor bolts. the existing anchorage 201 VBIT-1A CONTROL 108 Interaction 2: Three bay cabinets not Modification: connect cabinets at top.

connected at top.

524 VBXS-1B CONTROL 108 Bounding Spectrum #6: Relay under RL-2 Maintenance: Replace wire clip.

does not have a wire restraint clip.

525 VBXS-IC CONTROL 108 Boundmg_ Spectrum #6: lAwcr left relay Maintenance: Replace wire clip.

lacks wire restraint clip.

Table 5-4

SEQ ID NUMBER BUILDING ELEY OUTLIER DESCRIPTION OUTLIER RESOLUTION 526 VBXS-ID CONTROL 108 Bounding Spectrwn M: One small relay M=im-n=ce: Repiam wire clip.

does not have wire restraant clip (RL2).

529 WXS-3B CONIROL 108 Boundang Spectruan M: RL208 MOV208 Maname==nce Replace wire clip.

relay does not have a wire restraant. Same i

for RL205 (MOV 205).

531 VBXS-3D CONIROL 108 Boundang Spectnam M: RL208 & RL205 do Manaseanner Replacewireclip.

. not have wire restraint in pia .

un ca i

Table 5-4 i

O O O TABLE 5-5: List ofInaccessible items 18-Dec-95 BLDG ELEV REASON INACCESSIBLE RESOLUTION SEQ ID NO 19 CAHE-1 AUXILIARY 095 This item is ime for inspection. It is adjacent to two idenocal umts that have been verifm1 and it is therefore concluded that CAHE-F is Wh as well.

489 CAV-126 REACTOR 095 This item is inaccessible for inspecuon Inspecuon deferred to outage.

CONTROL 124 Interaction #5: Access of adjacent cabinets Walkdown deferred to outage 588 DRRD-2-2 not permitted by operauons CONTROL 124 Interaction #5: Access of adjacent cabinets Walkdown deferred to outage.

589 DRRD-2-3 not permitted by operauons INTER 136 Valve could not be seen. Walkdown deferred unut access can be 416 FWV-36 ci obtained.

A CONIROL 108 Bounding Spectrum #3: Transformer Walkdown deferred until out of operation.

513 MTSW-2C cabinet could not be opened to verify restraint.

CONfROL 108 Bounding Spectrum #3: Transformer Walkdown deferred until out of operation.

514 MTSW-2D cabinet could not be opened to verify restraint.

CONIROL 108 Bounding Spectrum #3: Transformer Walkdown deferred until out of operation.

515 MTSW-2E cabinet could not be opened to verify restraint.

CONTROL 108 Bounding Spectrum #3: Transformer Walkdown deferred until out of operation.

l 516 MTSW-2F l cannot be aacssed until it is out of service

( for maintenance.

CONTROL 124 Bounding Spectrum #6: Access of rear of Walkdown deferred until out of operation.

605 MTSW-3G-T #

cabinet not permitted by operations.

l i

CONTROL 124 Anchorage #1 arid Bounding Spectrum #7: Tug test deferred to outage.

606 MTXS-1 Access of cabinet to perform tug test not pernutted due to nuuntenance.

Table 5-5 .

( -

\

BLDG ELEY REASON INACCESSIBLE RESOLUTION SEQ ID NO AUXILIARY I19 Iparreccahle C--- , - - - in high-radassaan Walked down froaa photo oussade the 153 MUDM-1A area that could not be enterect roomt.

154 MUDM-1B AUXILIARY 119 Inaccessable Ca==paae='in high-radiataan Walked down from photo amande the area that could not be essered. rooms.

490 MUHE-IA REACTOR -095 This ince is inamecahle for incpersian incpereian deferred to outage.

491 MUHE-1B ' ,

REACTOR 095 This item is inurecahac for increriaan. lacpersian deferred to ousage.

492 M U H E-lC REACTOR 095 This item is inwrecahle for incaareiaa. Incperiaan deferred to outage.

125 MUr-1 AUXILIARY I19 l- ;ha,- Tank iaude locked high narmaer of ALARA, tank evaluated front radiation area. drawing a froni what could be seen 481 MUXS-1 AUXILIARY 095 Bounding Spectrum #3 & #7: Item could Walkdown deferred to outage, not be opened to assess internal

.,--__=

m 757 NI-1-A3 REACTOR 140 His item is innereaible for incaersiaa- Inspection deferred to outage.

m 758 NI-2-B3 REACTOR 140 His item is in-ahle for inspection. la<per1 aa deferred to outage.

759 NI-3-C3 REACTOR 140 This item is inaccessable for inspection. Inspectson deferred to outage.

760 NI-4-D3 REACTOR 140 This item is i-ch for inspection. lacpersion deferred to outage.

646 RC-002-TEI REACTOR 139 This item is in-code for inspection. Inspection deferred to outage.

647 RC-002-TE2 ,

REACTOR 139 This item is ia=reaihte for iariaa- Incperiaan deferred to outage.

533 RCPM-3A COMROL 108 Bounding Spectrum #1: Access not Walkdown deferred to outage.

permitted by operations.

534 RCPM-3B CONTROL 108 Bounding Spectrum #1: Arreu not Walkdown deferred to outage.

pernutted by operations.

716 RCV-13 REACTOR 145 This item is inacreuible for inspection. Inspection deferred to outage.

124 SFDM-1 AUXILIARY I19 Inaccessible: Tank in locked high radiation Tank was evaluated from photo aansade area. restncied area due to ALARA Table 5-5

_. _. .._ . . _ . . . - - _ . , _- ._ _ _ _ . .. . .- _ _ _ . . _~ . _.

. SEQ ID NO BLDG ELEY REASON INACCESSIBLE . RESOLUTION

-89 SWP-1A AUXILIARY - 095 Anchorage 1: Motorversacalrestraamtcould Walkdown of this itema (revisit) to n: solve not be seca in the field. issue will be erheshdad 97 SWP-1B AUX 1LIARY 095 Aarharage 1: Motor vertacal restraint could ' Walkdown of this itena (revisit) to resche not be seen in the fickL issue willbe N 104 SWP-IC AUXILIARY 095 Anchorage 1: Motor vertical restraint could Walkdown of this iteam (revasit) to sesehe not be seen in the field. issue will be schenhalent

~

883 WDT-1A AUXILIARY 095 Inarre=& Tanks are tarked in high Walkdown deferred until acxass can be .

redinanan area. abannervi

884 WDT-1B AUXILIARY 095 Ir==ne=shae Tanks are locked in high Walkdawn deferred until acce.s can be radiation area. ahaminad 885 WDT-IC AUXILIARY 095 la=me"shle. Tanks are locked in high Walkdown deferred until access can be radiation area. obtained.

783 WDT-5 REACTOR 095 His incan is innereah for inspection. Inspersian. deferred to outage.

m o>

! i Table 5-5 ,

i 1

i l

Table 5-6 Equipment Class Distribution - Mechanical and Electrical Equipment Equipment Class Number of Equipment Description of Class Items

. 0 3 Other 1 11 Motor Control Centers 2 17 Low Voltage Switchgear 3 5 Medium Voltage Switchgear 4 14 Transformers 5 40 Horizontal Pumps 6 7 Vertical Pumps 7 86 Fluid-Operated Valves 8A 36 Motor-Operated Valves 8B 91 Solenoid-Operated Valves 9 11 Fans 10 46 Air Handlers

/~l 11 2 Chillers V Air Compressors 12 12 j 13 0 Motor Generators 14 38 Distribution Panels 15 3 Batteries on Racks 16 14 Battery Chargers and Inverters 17 2 Engine-Generators 18 107 Instruments on Racks 19 27 Temperature Sensors 20 155 Instrumentation and Control panels and Cabinets TOTAL 727 57

6.. Tanks and Heat Exchanger Review 6.1 Summary of Review The tanks and heat exchangers on the Crystal River Unit 3 SSEL were evaluated in accordance with Section 7 of the PSP (Reference 2). The PSP is the same as the GIP in this section.

The seismic screening and walkdown included verification of 91 items of equipment that are classified as tanks or heat exchangers. These tanks and heat exchangers can be grouped as follows:

Total Number Grouping 8 Large flat bottom vertical tank 10 Vertical tank with legs 7 Vertical tank on steel base frame or skirt Horizontal tank on saddles I 5

2 Buried tanks O 17 Horizontal heat exchanger 2 Vertical heat exchanger 2 Coil type cooler (heat exchanger) 13 Small in-line heat exchangers/ coolers 18 Air Reservoirs 1

5 Cooling Units i 1 Gas bottles Twelve (12) bmks could not be walked down due to inaccessibility. A listing of those items and their status is provided in Table 5-5.

The results of the screening and walkdown are presented in the Screening Verification Data Sheet (SVDS) forms included in Appendix C.

O 58 j

{

' The only instances of intent but not letter of PSP caveat met were:

!O .

lV e Two horizontal tanks have cross bracing for the saddles. In these cases the  !

)

longitudinal frequency was assumed to be rigid rather than flexible (as determined I

by the PSP calculational method which ignores cross bracing).

e Six horizontal heat exchangers with saddle spacing greater than 20' (22' instead ,

of 20'). In these cases the heat exchangers are at grade, are rigid, and the l

' capacity is much greater than the demand.

A listing of equipment that meets the intent but not the letter of a PSP caveat is provided l in Table 5-3.

l 6.2 Summary of Outliers l The following general types of outliers were found. ,

~

j Caveats ,,

o Vertical tank not meeting the PSP calculation criteria for sliding and overturning e Poorly restrained gas bottles (on SSEL) j e Potentially loose longitudinal restraint of horizontal tanks e Anchorage design data (drawings and/or calculations) not yet located

[

N Interaction j e Potentially weak block walls in the turbine building l A listing of outliers and resolutions is provided in Table 6-1.

[.

No items were found to have Design Basis Deficiencies.

i k

d J

59

( ,, c.,

TABLE 6-1: Tsak and Heat Exchanger Outlier Description and Resolution Summary

18-Dec-95

! SEQ ID NUMBER BUILDING ELEV OUTLIER DESCRIPTION OUTLIER RESOLUTION 734 CDHE-4A TURBINE 095 Anchor bolts: Requires an anchorage Perform anchorage calculation.

evaluation.

735 CDHE-4B TURBINE 095 Anchor bolts: Requires an anchorage Perform anchorage calculation.

evaluation.

314 DFT-3A DIESEL 119 Connection: Strap is not secured to tank. Determine pretension on strap required to Tank might slide longitudinally. preclude slipping. Assure anchor bolts apply at least this level of pretension Flexibility of attached piping: If tank slides, it mq,ht cause loss of pressure boundary in attached piping.

315 DFT-3B DIESEL 119 Connection: Strap is not secured to tank. Determine pretension on strap required to Tank might slide longitudinally. preclude slipping. Assure anchor bolts apply at

@ Flexibility of attached piping: If tank slides, it might cause loss of pressure boundary in attached piping.

423 DHT-1 SOUTH BERM 119 Connection between concrete shield wall and Need to review how concrete shielding is tank could not be determined in the field. connected to tank (ifit is connected).

Anchorage type for the tank could not be Determine anchorage type and perform confirmed. calculation.

332 EFT-2 EFW TANK 119 Connections between anchor bolts and shell: Review original seismic tank calculation to Calculations indicate sliding and determine acceptability.

overturning capacity is less than guidelines require.

453 NGT-XX TURBINE 095 Caveat for anchor bolts: Bottles Bottles need 2nd restraint at 1/3rd height.

inadequately restrained.

18 WDT-3A AUXILIARY 095 Bounding Spectrum #2: Calculation needed Perform an anchorage calculation.

of anchorage adequacy.

Table 6-1

=

SEQ ID NUMBER BUILDING ELEV OUTLIER DESCRIPTION OUTLIER RESOLUTION 46 WDT-3B AUXILIARY 095 Bounding Spectrum #2: Calculation needed Perfonn an anchorage calculation.

of anchorage adequacy 59 WDT-3C AUXILIARY 095 Bounding Spectrum #2: Calculation needed Perform an anchorage ab i-*ina_

of anchorage adequacy l

l 3

f Table 6-1

i

7. Cable and Conduit Raceway Review The Crystal River Unit 3 cable and conduit raceways were reviewed and evaluated in Appendix B of Reference 6. The conclusion of this review is as follows:

" Based on the good performance in past earthquakes of raceways not designed for earthquakes and constructed to normal industrial practice, the fact that CR3 safety-related raceways were originally designed for and later re-evaluated for earthquakes, and the fact that Crystal River Unit 3 is a low seismic site, in our judgment the raceway systems at CR3 meet the intent of the GIP. Thus, a case by case review of the raceway systems at CR3, to the screening guidelines in the GIP or to any other guidelines in addition to the raceway seismic criteria used at CR3, is not needed to satisfy GL 87-02.

"This judgment is supported by supplementary calculations interpreting the basis for the GIP vertical capacity guideline to infer a CR3-specific GIP-like guideline, and calculations interpreting the CR3 raceway design criteria in terms of GIP guidelines." )

Additionally, it was noted in the Third Party Review that beam clamps are sometimes used with the clamp mounted on a vertical member (possibly subject to slipping). This configuration is  :

common in the Turbine Building and instances were also found in the other buildings. A I walkdown was performed to review these clamps to determine whether or not these might ,

adversely affect the seismic performance of the raceway. An extensive walkdown resulted in no identified problems. In general, the beam clamps are lightly loaded (typically, the support j O. spacing throughout the plant is approximately half that allowed by the GIP). These clamps also were load tested during the walkdown (loads of several hundred pounds) with no indication of potential slipping. The conclusion, is that the beam clamps do not adversely affect the seismic performance of the raceways. l l

There are no raceway outliers and raceways require no further action.

1 i

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1

.rms 8. Plan for Addressing Unresolved Outliers  !

U Tables 5-4 and 6-1 summarize the resolution or status of each of the outliers. The outliers have l

been evaluated against the current licensing and design bases and no deviations were found. The outlier resolution presented in the tables is based upon the best information available at this time.

As more information becomes available, the resolution may change. Detailed schedules have not been formulated; however, the general plan will be as follows:

For outliers which can be resolved through routine maintenance, Work Requests will be generated and the problems will be corrected as part of the normal work control process. One exception to this is the Control Room ceiling. Additional work will be required to ascertain the i

, design configuration, evaluate its seismic adequacy, and devise a configuration control method to maintain the proper configuration. For outliers where the plant is in the design configuration, but still does not meet the PSP criteria, Project Authorizations will be prepared and scheduled in accordance with the Crystal River 3 Master Scheduling Program.

It is FPC's intent that all outliers be resolved by the end of Refuel 12, in the Spring of 2000.,

l V, 4

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63 I

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i 0 9. Significant or Programmatic Deviations from the PSP 4

j There are no significant or programmatic deviations from the Crystal River Unit 3 PSP l (Reference 2).

(

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10. Third Party Audit Summary l A third-party audit was performed by Mr. Charbel Abou-Jaoude. He prepared his comments based on a review of the Technical Basis Report, the PSP, and a broad sampling of each of the 20 SQUG classes, tanks and heat exchangers, and electrical raceways. The audit resulted in four comments on the Technical Basis and four comments from the field reviews. These comments

) have been addressed through further evaluation by the SRT. Mr. Abou-Jaoude's third party l audit report is provided in Appendix D.

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11. References

(.p) 1

1. Generic letter 87-02, " Verification of Seismic Adequacy of Mechanical and Electrical )

Equipment in Operating reactors, Unresolved Safety Issue (USI) A-46," U.S. Nuclear

. Regulatory Commission, Washington, D.C., February 19, 1987.

2. " Florida Power Corporation Plant Specific Procedure (PSP) for Seismic Verification of Nuclear Plant Equipment", Revision 1, September 8,1994.

3. Florida Power Corporation letter to the Nuclear Regulatory Commission, dated August 27,1993.

4. USNRC, " Supplement No. I to Generic letter (GL) 87-02 that Transmits Supplementary Safety Evaluation Report No. 2 (SSER No. 2) on SQUG Generic Implementation Procedure," Revision 2, as corrected February 14, 1992.

5. " Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment," dated February 1992, copyright Seismic Qualification Utility Group (SQUG), Revision 2, corrected February 14, 1992.

6. " Technical Basis for the Crystal River Unit 3 Plant Specific Procedure to Resolve NRC Generic Letter 87-02", Revision 0, June 1993.

7. Nuclear Regulatory Commission letter to Florida Power Corporation, dated April 12, 1994. .

1

8. Crystal River Unit 3, Final Safety Analysis Report.

9. Florida Power Corporation letter to the NRC, 3F1088-04, dated October 7,1988,

10. Florida Power Corporation letter to the Nuclear Regulatory Commission, dated August l

I 15, 1994.

11. Florida Power Corporation letter to the Nuclear Regulatory Commission, dated September 16, 1994.

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, - - - - -----n- - - - - . . . - - - - . . ~ - - - - - - - - - - . . - - - - - - - - - - - , - . - - - . . - . - - -

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l FLORIDA POWER CORPORATION l

CRYSTAL RIVER UNIT 3 l

l k

l APPENDIX A

! RESUMES FOR SEISMIC CAPABILITY ENGINEERS

~

i lO

i Appendix A Resumes for Seismic Capability Engineers

Anthony Petrowsky, FPC Supervisor Nuclear Engineering Daniel L. Jopling, FPC Senior Nuclear Structural Engineer

< Joe A. Iese, FPC Senior Nuclear Structural Engineer C. Glenn Pugh, FPC Senior Nuclear Structural Engineer 4

John O. Mascoll, FPC Project Engineer Paul Smith, The Readiness Operation, Inc.

Harry Johnson, Programmatic Solutions, Inc.

Donald Rutherford, Programmatic Solutions, Inc.

' Charbel Abou-Jaoude, VECTRA Technologies, Inc.

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Anthony Petrowsky ,

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Homosassa Springs, FL 34447 l (904) 382-3482

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SUMMARY

oualified by 25 years of progressive engineering experience complemented by an excellent academic foundation including a Master of Science in Civil and Structural Engineering.

1 EXPERIENCE:

1/90 to Present SUPERVISOR, NUCLEAR ENGINEERING DESIGN FloridaPowerCosporaten Supervise Structural Design Engineering Group within the Nudear Engineering Design Department. Responsible for the design and implementation of structural related backfit modifications for Crystal River Unit 3 Nuclear Power Station. Previous duties in this capacity included supervision of the Mechanical / Structural Design Group. Responsibility changed following the re-organintion of the Engineering Department when the corporate engineering staff was relocated to the plant site.

11/87 to 1/90 PRINCIPAL NUCLEAR STRUCTURAL ENGINEER Florida fowerCorporation Developed standardized design and acceptance criteria for structural related projects, implementation of vendor supplied computer software for nuclear safety related engineering anaiy;f Acting supervisor for structural and as-building functions within the

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Nuclear Operations Engineering Department.

4/84 to 11/87 SENIOR NUCLEAR STRUCTURAL ENGINEER FloridaPowerCorporation

>V Responsible for the design of structural related backfit modifications for Crystal River i Unit 3 Nuclear Power Station.

2/82 to 4/84 LEAD SENIOR ENGINEER Impell Corporation, Atlanta GA Functioned as a consultant to Florida Power Corporation on field assignment from 2/82 to 10/83. Upon return to corporate office, functioned as Assistant Project Engineer for Duke Power's Catawba Unit 2 Nuclear Power Station. Responsible for the final review and approval of design calculations and drawings associated with the Reactor Building nuclear piping systems. Responsible for the direct supervision of 20 design engineers assigned to the Duke Project.

1/81 to 2/82 DESIGN ENGINEER Ebasco Services Incorporated, Atlanta GA Perform analysis and design of major generating plant structures for a 2 Unit,600 MWe fossil plant located in Jacksonville FL.

9/78 to 1/81 PROJECT CIVIL ENGINEER Florida Powerd Light Company, Miami, FL l Duties included directing and overseeing all civil engineering functions associated with  ;

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. the design and construction of St. Lucie Unit 2 Nuclear Power Station.

1 4/70 to 9/78 PRINCEPAL ENGINEER Commonwealth Edison Company, Osicap IL l

'f Progressive responsibility and promotions, beginning with design and construction of EHV Transmission Facilities. Subsequently transferred to Station Nuclear Engineering Department, responsible for technical evaluation of potential sites for both nuclear and fossil generating stations. Also initiated and directed engineering investigations and ,

laboratory testing to obtain empirical structural design data for the purpose of reducing design conservatism and cost in the construction of Nuclear Power Stations.  !

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i Anthony Petrowsky PO Box 1014 e Homosassa Springs, FL 34447 (904) 382-3482 i

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, EDUCATION: ILLINOIS INSTITUTE OF TECHNOLOGY - Chicago, Illinois Mauer of Science in Civil / Structural Engineering 1976 SOUTHERN ILLINOIS UNIVERSITY - Carbondale, Illinois Behelar of Science in Civil Engineering 1970

AWARDS

Selected as 1975 participant in Commonwealth Edison " Advanced Technical Studies Program". This awards a one year paid sabbatical to pursue graduate studies in engineering.

PUBLICATIONS: Presented paper to the American Society of Civil Engineers entitled " Underground Pumped Storage for Commonwealth Edison" 1976. ,,

. Published paper entitled " Reducing Deflections in Steel Poles by Concrete Fdling" in Electric 1.icht and Power. November 1973.

CERTIFICATIONS: Registered Professional Engineer - Morida and Illinois PERSONAL: Excellent Health.. Single f'

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REFERENCES:

Excellent personal and professional references are available and will be furnished l upon request.

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i David A. Freed, MPR Associates Robert P. Kassawara. EPRI SQUG Training Coordinator SQUG Program Manager I  ?

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Daniel L Jopling, P. E.

q RESUME EXPERIENCE SYNOPSIS A Professional Structural Engineer with a diverse engineering background in architectural structures as well as structures unique to the nuclear industry, Representing a progressively responsible involvement in structural engineering:

- Analysis and design involving; static and dyn&mic analysis of steel, concrete, masonry and timber structures applying numerous computer codes as well as hand analysis techniques. Analysis efforts addressed dead load, wind, seismic, and other static and dynamic loadings. Design efforts applied local and national building code requirements as well as ACl, ASME, AISC specifications.

- Project Manager; responsible for development of project scoping documents, schedules, technical instructions, cost control, interface with subcontractors as well as review and approval of results.

- Client relations activities; marketing, bid preparation, proposal preparation and in-house personnel tra;ning .

REPRESENTATIVE PROJECTS

- Lead Engineer; Boron Corrosion Inspection Crystal River 3, Florida Power Corp.

Development of inspection program for boric acid corrosion inside containment, direction of project team, assessment of results and final close out report.

- Project Manager for a facility addition; Federal Emergency Management Agency (FEMA), US Corps of Engineering Total scope, preparation of construction documents including arenitectyral subcontractor for a $3.5 million faci!ity expansion.

4 - Project Engineer for Qualification of the Unit 2 Cable Spread Room Frame; Comanche Peak Steam Electric Statio'n, T U Electric Development a simplified approach for the dynamic (seismic) analysis and qualification of a complex frame structure.

- Project Engineer for the development of preliminary Rupture Restraint Design; Sizewell B Nuclear Station, CEGB United Kingdom Development of restrains criteria, training local design team and development of foot print loads.

i (D EMPLOYMENT HISTORY Florida Power Cooperation; Senior Nuclear Structural Engineer; responsible for structural design and analysis efforts, including seismic qualification for the Crystal River Unit 3 Nuclear Plant.

Crystal River, Florida (1991 to present)

ABB Impell; Section Manager; responsible for a consulting engineering business unit Ft. Worth, Texas; Manchester, United Kingdom; Knoxville Tennessee; Atlanta, Georgia; Charlotte, North Carolina (1981-1991, 1978-1979)

Piping Design Services (PDS); Senior Engineer; analysis and design activities for safety related structures Richland Washington (1979- 1981) i Mathews Corporation; Structural Designer Tampa, Florida (1972-1978)

U. S. Army; Drafter Republic of Vietnam; Fort Belvoir, Virginia (1970-1972)

EDUCATION and PROFESSIONAL QUALIFICATIONS Bachelor of Science in Engineering (Structures) University of South Florida Tampa, Florida Professional Engineer Florida (Structural) 31121 Georgia (Civil) 13623 Texas (Civil) 66911 Member American Society of Civil Engineers (O

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JOSEPH A. LESE Seruor Nuclear Stmetural Engsneer A

Twenty yars experience in structural design work in both ojJice andfield environments. Major emphasis given to on. site assignments at nuclear generatingfacilities performing design modification work and resolving corutmetion problems.

EXPERIENCE: Florida Power Corporation since 1989 1989 to CrystalRiver Nuclear Power Station, Unit #3. Provide on site engineering supportfordesign modification present packages, including the seismic design of electrical raceway supports. Also, responsible for structural engineering support in the areas of the tendon surveillanceprogram, Control Complex Habitability Envelope interfaces, and long term on site radwaste storage.

1986-89 GilbertlCommonwealth (GIC) since 1975 Crystal River Unit #3, Crystal River, FL. Provide contractor interfacefor the modification of electrical raceway hangers being upgraded for Appendit 'R' considerations.

1965 Tennessee Valley Authority, Knoxville, TN office. Performed structural design and review ofpipe support variances for Bellefonte Nuclear Power Station, Scottsboro, Alabama.

1984 Perry Nuclear Power Plant, Peny, Ohio. Site structural design team member responsiblefor administration offield change requests, nonconformances, field questions, and engineering change notices under contract to the Cleveland Electric illuminating Company. >

1963 GlC home office in Reading, PA assigned to design team for the analysis ofjet shields for Peny Nuclear Power Plant. Design incorporated shielding of critical components from postulated pipe breaks and resultant pressure loadings.

1982 R.E. Ginna Nuclear Power Station, Rochester, NY evaluated existing wallsfor resistance to waterpressure f due to flood loads.

Q 1981 Washington Public Power Supply System, Hanford, WA. Design and review of Class Iand 11 pipe supports.

GlC home offi.e in Reading, PA. Design offoundations, manholes, and ductbanks for Peny Nuclear Power Plant.

1980 GlC home office in Reading, PA. Seismic design of raceway suppons for the VC Summer Nuclear Generating Station, Jenkinsville, SC Seismic design ofpipe supportsfor General Public Utilities' Three Afile Island Unit #1 per USNRC bulletins 79-02 and 7914.

1979 YC Summer Nuclear Station, Jenkinsville. SC On. site design of system supports and resolution of constntction problems associated with same.

1978 GlChome ofJice in Reading, PA. Seismic design ofduct, cable tray, and conduit supportsfor VC Summer and Peny Nuclear Power Plants.

1975 77 Engineering Technician at GlC oJJice. Assisted structural engineers in the desip ofsystem supports through calculations.and computer modeling.

1974 Pennsylvania Department of Transportation, Radnor, PA ,

Engineering Technician involved in environmental noise and air studies for Interstate 95 construction l project in Philadelphia, PA.

EDUCATION: B.S. Civil Engineering, Drexel University,1978 A

REGISTRATION: Professional Engineer - Pennsylvania (1931) l

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SQUG T- 9 roordinator SQUG Program Manager 1 1 1

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Resume C. Glenn Pugh, P.E.

O EXPERIENCE SYNOPSIS:

A Professional Engineer with a diverse engineering background. This background includes the structural design and analysis cf commercial, industrial, and power generation (fossil, nuclear, and cogeneration) facility designs.

Analysis and design activit'es have involved the static and dynamic (seismic) analysis of steel, aluminum, wood, concrete, and masonry structures. Analytical efforts included numerous computer programs (both PC based and main-frames) also hand analysis techniques. Structural designs comply with local, and national building codes, including ASME, AISC, ACI, and other similar standards. Further experience includes extensive field inspection /walkdown of construction activities and operating plant equipment.

REPRESENTATIVE PROJECTS:

The following is a partial list of projects responsible for, or as having served as a team member:

> Project Engineer responsible for resolving the NRC's Unresolved Safety Issue (USI) A-46 at Crystal River Unit 3. Further, acted a lead engineer in the development of the site specific plan to address seismic safety issues for the plant.

• Responsible for a group of engineers and designers who participated in the design verification of conduit systems at a nuclear power plant. Participated in the development of a typical conduit span / support analysis document and computer software.

> Piping analysis and pipe support design for various auxiliary systems at a chemical recovery boiler project.

> Perform seismic and dynamic analysis on steel and aluminum water storage tanks.

> Perform rigorous piping analysis (deadweight, thermal, and seismic) and pipe support designs.

> The design and analysis of steel structures supporting equipment, platforms, and piping. This included

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V detailed analysis of connections, base plates, member stresses, member selection, and deflections calculations.

> Construction support, including on-site coordinator between craft, vendors, client and office engineering staff. Also includes extensive field and piping walkdown experience.

EMPLOYMENT IIISTORY:

i i Florida Power Corporation; Senior Structural Engineer; 11/91 to present.

ABA Impell Corporation; Lead Senior Engineer; Supervising Engineer; 3/90 to 11/91.

Rust International Corporation; Engineer II; Design Lead Engineer; 4/88 to 3/90.

Impell Corporation; Engineer 11; Principal Engineer; Senior Engineer; Lead Senior Engineer; 6/81 to 4/88.

Babcock and Wilcox Company; Associate Engineer; 3/80 to 6/81. i EDUCATION

University of South Florida, Tampa, Florida, Bachelor of Science in Engineering, Civil / Structural emphasis.

SQUG Walkdown Screening and Seismic Evaluation training Course.

REGISTRATIONS:

Registered Professional Engineer:

Florida, 41451 Alabama,17403 Tennessee,19217 Wisconsin, E-27211 Michigan, 6201036425 p)

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PROFESSIONAL AFFILIATIONS:

American Society of Civil Engineers

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John O. Mascoll Home : (404) 446-9688 5007 Holbrook Circle, N.W. Work : (817) 897-8913 l Duluth, Georgia 30136 Contact : (404) 329-6523 j l

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CAREER OBJECTIVE I am interested in a Civil / Structural position where complete technical reliability and the ability to produce on the-spot research solutions are required. j i

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• Senior Engineer, ABB IMPELL CORPORATION, CENTRAL REGION, Fort Worth, Texas. (January 1991 to present). )

Currently assigned to Texas Utility's CPSES Unit 2, Scope "C" Project. I am involved i

In a four-man task team which is responsible for the design validation and approval

O of Unit 2 plant-wide emergency lighting system. Other responsibilities include the

,V design validation and generation of footprint loads for electrical conduit and lighting fixture supports, utilizing Impell's "NEWCOND1" Computer Program and X/PD STRUDL Program.

Senior Structural Engineer, VIATECH SERVICES, INC., Birmingham, Alabama.

(October to December 1990).

Assigned to Southern Company's Vogtle Support Group, where I was involved in a snubber reduction program for Georgia Power Company's 'Alvin W. Vogtle Nuclear Plant.' My responsibilities included the interpretation of autopipe and ME101/M3 piping analysis, so as to justify the reduction of mechanical snubbers and the effect of this reduction on the remaining structural pipe supports. Re-evaluation and/or design changes of the affected piping supports was also required.

Advanced Structural Eneineer, SIMONS-EASTERN, INC., Atlanta, Georgia.

(September 1988.to October 1990).

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i Responsibilities included the analysis and design of partially open steel structures consisting of metal decking roof, purlins, rigid frame, fiberglass siding, pin column, pier and spread footing, monorail and two railroad tracks inside of building. Pile cap 1 foundations, pile supports, pipe bridge and towers, pile cap foundation and piers for l q towers and columns. All the above activities performed for Federal Paper Board Pulp Q Mill, Augusta, Georgia, and Parsons & Whittemore's Alabama Pine Paper Mill Project.

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Advanced Stmetural Engineer. RUST INTERNATIONAL, Birmingham, Alabama.

Qune 1988 to September 1988).

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Responsible for analysis and design of steel framings to support roofing and decking; -

! steel columns; and girts to support metal sidings. Checked existing foundations and  :

designed new foundations to support three-story buildings.  !

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j Structural Steel / Reinforced Concrete Design and Retrofit Services, IMPELL I

CORPORATION SOUTHEASTERN /SOUTHCENTRAL REGION. Ganuary 1981 to

June 1988). j i Started as an Engineer I. Developed a broad background in stmetural, dynamic, and seismic analysis of complex frames and equipment supports which encompassed a ,

, wide variety of technical tasks. Advanced to Senior Engineer. Responsible for organizing pertinent technical data and design specifications in order to develop ,

analytical and field inspection procedures. These were then used in executing

sophisticated analysis of non linear systems, and in analyzing structural and electrical

) components for vibrational / dynamic loading. The process involved the use of computerized programs such as MCAUI'O STRUDL and GTSTRUDL, Finite Element, i Base Plate II, and AUTO CAD. Also utilized a variety of structural codes and

. references. During this time I completed employer sponsored in-house training course in Project Engineering Management, for which I was awarded a certificate.

i Accomplishments included assignments for the following:

l . Duke Power Company's McGuire Nuclear Power Plant. Designing and checking ,

piping supports to comply with NRC'sBulletin 79-14.

! . Duke Power Company's Catawba Nuclear Power Plant. Designing pipe supports L and rupture restraints for Unit I and II. Designed new safety-related supports to comply with ASME Section III, Subsection NF.

! . Southern Company Services, Plant E. I. Hatch. Cable Tray Re-qualification and l- Appendix "R" Project, and Vogtle Support Analysis Group.

. Tennessee Valley Authority, Watts Bar Nuclear Power Plant. Pipe support and

rupture restraint project to comply with ASME Section III, Subsection NF.

. Tennessee Valley Authority, Browns Feny Nuclear Power Plant, Unit IL Designing and checking supports for the control rod drive system modification

project.

, . TU Electric, Comanche Peak. Designing and checking Train "C" conduit support )

modifications for Unit I and II and rotating equipment qualificat'om O

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• Earlier Experience-BARBADOS WATER AUTHORITY, Barbados, West Indies). Gune 1972 to December 1975).

j Started as a Structural Draftsman. Responsibilities included the preparation of site development plans, and locating and designing storage areas for heavy duty construction equipment. Advanced to Engineer's Assistant. Performed calculations for the design of stmetural steel, reinforced concrete columns / column footings, widespan beams and reinforced concrete roofing. These tasks were required in the 3 constmction of several underground reservoirs with a holding capacity of one to two million gallons of drinking water.

Education:

, (Six credit hours taken towards the Master's degree in Civil Engineering through

} University of South Carolina, Columbia).

B.E., Civil Engineering. Vanderbilt University, Nashville, Tennessee. Graduated December,1980.

B.S., Physics. Fisk University, Nashville, Tennessee. Graduated December,1980.

Graduated from the Samuel Jackman Polytechnic, Barbados, West Indies. Awarded certificates in Technical Drafting, Economics, and English Language.

Erofessional Associations Associate Member, American Society of Civil Engineers.

Personal Data Born August 15,1951 in Barbados, West Indies...U.S. citizen since 1986... Married; two children... Height,6'-1"... Weight,195 lbs... Health, excellent.

1978 and 1979 ' Dual Degree Student of the Year, Fisk and Vanderbilt Universities.

1979 - NCAA All American in decathlon and long jump.

1979 - Pan American Games participant.

,{ - Interests include wood-working, weight-training, racquetball, and outdoor activities.

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i References 1

4 i These can be furnished upon request.

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1 President i Paul Smith The Readiness Operation,Inc.

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Education University of Califomia - PhD in CiviVStructural Engiacering,1971 l

Lehigh University - Master of Science in Civil /Stmetural F ming,1964 University of Akron - Bachelor of Science in Civil Engineering,1962 l;

Licenssa and Registrations Civil Engineer - California C 24377 )

Professional History The Readiness Operation, Inc Oakland, Califomia - President,1989 to present l EQE, San Francisco, California - Senior VP, Board of Directors, 1984 - 1989 4

Lawrence Livermore National Laboratory, Livermore, Califomia - Associate j

Program Leader for Seismic and Structural Safety,1976 - 1984 1974 - 1976 EDS Nuclear (Impell), San Francisco, Califomia - Supersising Engineer, i

Aubum University, Alabama - Assistant Professor of Civil Engineering. 1971 - 1974 l

J Marshall Spaceflight Center, Huntssille, Alabama - NASA-ASCE Fellow,1972 1 % 7 - 1971 University of Califomia, Berkeley - Teaching and Research Assistant, Bechtel, San Francisco, Califomia - CiviUStructural Engineer,1%7 l

US Army, Fort Belvoir, Virginia Engineering Officer,1%5 - 1%7 i Shell Oil, New Orleans, Louisiana - Civil / Structural Engineer, 1964-1965 Bethlehem Steel, Bethlehem, Pennsylvania - Cisil/ Structural Engineer,1%3 Burger Iron, Akron, Ohio - Structural Steel Designer / Drafter,1952 - 1962 s l i

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Experience l Dr Smith has over 30 years ofvaried experience in earthquake and stmetural en-i gineering and in university teaching. He has managed large teams of research and desi engineers on projects ranging from nuclear power plants to industrial, commercial, and

' public facilities. In recent years, he has developed a number of seismic training courses.

Dr Smith is currently performing Peer Revins for USI A46 and the IPEEE for l Florida Power and Light, Philadelphia Electric, ani Wisconsin Public Service; participat-ing in the implementation of the Seismic IPEEE for ClevelandElectric //luminating; ,

leading the development of a plant specific A46 and Seismic IPEEE program for Florida l

' Power Corp, and consulting on A46 and the Seismic IPEEE for Public Service Electric &

Gas ofNJ, Virginia Power, and Yankee Atomic Electric.

Dr Smith also organized a national workshop on the Seismic IPEEE, and has been

the primary advocate of simplifying and reducing the costs ofimplementation of both the A46 and the Seismic IPEEE.

In nuclear research, Dr Smith is best known as the developer and manager of NRC's Seismic SafetyMargins Research Program (SSMRP). The SSMRP completed the seismic probabilistic risk analysis (PRA) efYorts NRC began in the Reactor Safety Study, and developed Seismic PRA technology for the Seismic IPEEE. Dr Smith also in-itiated two well-known spin-off's from the SSMRP: (1) the Load Combination Program

' (which led the NRC to revise piping criteria and adopt the leak before break philosophy),

and (2) the Seismic Hazard Characterization of the Eastern United States Program (to de-velop a more stable estimate of the earthquake hazard to benefit both NRC and the indu

- try) which developed seismic hazard technology for Seismic PRAs for the Seismic IPEEE.

Tbe Readiness Operation

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Dr Smith also initiated the Seismic Design Margin Program (which developed l I i# NRC's Seismic Marf'n approach for the Seismic IPEEE). Prior to the S j of seismic design margins. He has been at the forefront of developing improved c .

for seismic destyi for some time.' sed efforts on the seismic, tornado, and hurricane anai i

Dr Smit s also su the mooring system and eakwater for the Atlantic Generating Station (the floating nu-l clear power plant).Dr Smith is one of the founders of using data from past earthqua j

NRC Unresolved Safety Issue A46: Seismic Qualification of Equipment in Oper.

j sfing Plants. His NUREG/CR-3017 was a key step in helping NRC issue its first w

• ten recognition of the feasibility of using these data for A46 and for the seismic verifi

' tion of equipment. In his five years at EQE, he was a consultant to the Seismic Qua i tion Utility Grou p on A46, and initiated many other applications of this new technology; for example, cabie tray, conduit and piping systems, tanks, anchorage, and cranes. H helped develop and present training programs on SQUG/ GIP technology. As EQE j the conduit / cable tray approach that was ultimately license i

SQUG's conduit / cable tray methodology, and obtained SSRAP and NRC approv Dr Smith has attended the SQUG Seismic Capability Engineer traimng course.

! Dr Smith is one of the key developers of EPRI NP-6628: Procedurefor Selsm/c Evaluation and Design of Small Bore Piping (NCIG-14), which used earthquake experi-ence data to justify a " design by rule " approach for piping. N l buildings, bridges, and offshore structures.Dr Smith has represented the US G l

changes on earthquake engineering, including NRC scientific exchanges with Japan 1979 and 1982, Korea in 1982, Europe in 1979 and 1983, and Taiwan in 1984.

l Selected Publicatians l Publisher and 'iditor of the Earthquake Safety & Licensing Report **, A monthly 1.

newsletter on (nuclear) Industry earthquake safety, ISSN 104$.7895.

l Seismic Qualfcation Using Earthquake Experience Data, Nuclear News, June 1989.

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3. Correlation ofSeismic Esperience Data in Non-Nuclear Facthries with Seismic Equipment l

Qualifcation in Nuclear Plants (A 46), prepared for the U.S. Nuclear Regulatory C l

sion by Lawrence Livermore National Laboratory, NUREG/CR-3017, Nov.1982.

4. SQUG Cable Tray and Conduit Evaluation Procedure, Second Symposium on Cur-l rent issues Related to Nuclear Power Plant Structures, Equipment and Pip-j e

ing, Orlando, December 1989.

5. Procedurefor Seismic Emluation and Design ofSmall Bore Piping Developed by

! EPRl/NC/G, Third Symposium on Current issues Related to Nuclear Power l

Plant Structures, Equipment and Piping, Orlando, December 1990.

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6. Seismic Margins in Piping Systems, in Proceedings,1990 Pressure Vessel And l

Piping Conference, American Society of Mechanical Engineers, Nashville,1990.

7. Recommended Piping Seismic Adequacy Criteria Based on Performance During and Afte Ferthquakes, EPRI NP 5617 prepared for Electric Power Rosearch Institute,12/88.

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8. Independent Seismic Walkdown Review Team (ISWRT) Critique ofSRSSQUG Type 1

Seismic Programfor Restart ofK-Reactor at the Savannah River Site, prepared by ISWRT for the US Department of Energy, February and April 1990.

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9. Dr Smith is one of the significant contributors identified by SQUG for their Generic /mple-l mentation Procedure (GIP)for Seismic Verification ofNuclear Plant Equipment, Seismic Qualification Utility Group (SQUG), February 14,1992.

( 10. Towards Future Antiseismic Criteriafor Nuclear Plant Piping Systems, to be pub-lished in ASME Special Publication: Technology for fhe 90s.

11. Peer Reviewfor USl A46 and the Seismic IPE, to be published in ASME PVP 1993.

j Tbe Readiness Operation

Training Courses Developed and Presented "Owrview ofSeismic IPE and USI A-46. " Developed and presented with Programmatic Solutions. One day course presented in open enrollment sessions.

"Trainingfor Engineers and Designers in SQUG Methods. " Developed and presented with Programmatic Solutions. Twc, day course presented on-site and in open enrollment.

"Using SQUG MethodsforModifications andReplacements. " Developed and presented with Programmatic Solutions. Two day course presented on site and in open enrollment.

"On-Site Overview of SQUG Methods and Their Usefor Modification and Replacements. " Developed and presented with Programmatic Solutions. Three hour overview course for management presented on-site.

" Basic Seismic Engmeering. " Developed and presented with Programmatic Solutions.

l Two day course presented on-site and in open enrollment.

"SeismiclPE Workshop." Developed and presented with Programmatic Solutions. Two j day workshop presented in open enrollment.

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4 PROGRAMMATif' SQL11TIONS l

I Harry W. Johnson

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Edacatloa Colunbia University - Meenanics Engineer,1968 l University of Miami - Master of Science in Civil Engineering,1%7 University of Miami - Bachelor of Science in Civil Engineering,1965 Bettis Atomic Power Laboratory - Reactor Engineering School,1972 j SQUG Walkdown Screening and Seismic Evaluation Training Course,1992 I Licenses and Registrations

<' California: Civil Engineer i

Professional History Programmatic Solutions,1992 Robert L. Cloud & Associates, Inc, Senior Associate, 1990-1992 l

2 EQE Engineering, Senior Associate, 1986-1990 Impell Corporation, Section Manager, 1974-1986 l/ Westinghouse Bettis Atomic Power Laboratory, Senior Engineer, 1969-1974 i Cornell Aeronautical Laboratory, Project Engineer, 1968-1969 4

Experience Mr. Johnson has over 20 years experience in engineering consulting in the l

power industry. In particular, Mr. Johnson has extensive experience in project l

management and design engineering.

L Mr. Johnson is currently performing Peer Reviews for USI A-46 and/or

• IPEEE for Peach Bottom 2 & 3 and Limerick I & 2, Salem Units 1 & 2, Arkansas Nuclear One Units 1 & 2, Grand Gulf, and Waterford. Mr. Johnson is also l

performing Peer Review of experience based piping re-evaluation for the Brookhaven National Laboratory HFTR, performing a QA Audit of Seismic Programs for Indian Point Unit 2, performing USI A-46 walkdown for Indian Point Unit 3, helping to develop a plant specific seismic program to address USI A-46 for Crystal River, participating in the implementation of the Seismic IPEEE for Perry, and providing l

EPRI/PSE sponsored training for Seismic Technical Evaluation of Replacement Items

! and for Use of SQUG Methods for New and Replacement Equipment.

s

PROGRAMMATir ROI11TIONR Mr. Johnson has performed SQUG type seismic verifications for Peach Bottom, Vermont Yankee, Pilgrim, Three Mile Island, Oyster Creek, Maine Yankee, O Princeton Tokamak (TPTR), Savannah River Project, Cruas (France), Sequoyah, and Indian Point Unit 2.

For TVA Bellefonte, Mr. Johnson developed an implementation strategy for the overall IPEEE program (all external events).

Mr. Johnson has performed Independent Peer Reviews of comprehensive seismic interaction programs at Watts Bar and Comanche Peak and of the equipment seismic qualification program at Watts Bar.

Mr. Johnson has participated in the development of SQUG training programs, and developed the original draft of training for the SQUG seismic interaction modu Mr. Johnson (along with Paul Smith of TRO) developed a 2 day training course in SQUG walkdown methods which has been presented to GPU Nuclear, PSE&G of New Jersey, Rochester Gas & Electric, New York Power Authority, Carolina Power

& Light, Martin Marietta, Stone & Webster, and Gilbert / Commonwealth.

Mr. Johnson is heavily involved in applying SQUG methods to nuclear procurement programs, and is active in industry initiatives in this area. To date Johnson has managed the development of these methods for seven plants. Mr.

Johnson is a contractor for EPRI/PSE in the development of Seismic Technical Evaluation of Replacement Items (STERI) and Generic STERI (GSTEIU).

At EQE Mr. Johnson started up and managed the Eastem Regional Office.

Project work included development of new methods for seismic evaluations of mechanical and electrical equipment using SQUG methods. For GPU Nuclear, Mr.

Johnson developed and managed all work associated with the seismic verification of TMI and OCNGS control room cabinets, including verification of many l modifications. -

At Impell Mr. Johnson was Manager of Engineering Mechanics. This included design, project management and engineering evaluations.

j I

At Bettis Mr. Johnson haded a reactor engineering stress / test group for an advanced submarine project.

At Cornell Aeronautical Laboratory Mr. Johnson performed projects related to

' automobile crash injury research.

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' Selected Publications

" Guideline for the Seismic Technical Evaluation of Replacement Items for Nuclear 2

Power Plants (PSE-01)", EPRI NP-7484.

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PROGRAMMATIC Rn111TIONS "Use of Seismic Experience Data for Replacement and New Equipment", Nuclear Engineering and Design,1990.

" Application of Industry Experience Data to Equipment Qualification", Third Symposium - Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping, December 1990.

" Impact of General Procurement and Commercial-Grade Item Initiatives", Third Symposium - Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping, December 1990.

" Integration of Seismic Technical Requirements for Replacement items into Nuclear Plant Design Basis", to be presented at ASME PVP Conference, June 1992.

" Role of Seismic Engineers in CGI Technical Evaluations", Earthquake Safety &

Licensing Report, June 15, 1992.

" Site Specific Procedures for Seismic Verification Walkdown for a Nuclear Plant".

Fourth Symposium - Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping, December 1992.

" Peer Review for USI A46 and Seismic IPE", presented at ASME PVP Conference, July 1993.

" Integration of Seismic Qualification in the Engineering Change Process", presented ,

at Fifth Symposium - Current Issues Related to Nuclear Power Plant Structures,

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Equipment and Piping, December 1994. i i

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l PROGRAMMATIC SOLUTIONS, INC. I DONALD H. RUTHERFORD Senior Associate l

Education Massachusetts Institute of Technology, MSCE (Structures).1969 Massachusetts institute of Technology, BSCE,1967 SQUG Walkdown Screening and Evaluation Training Course Summary of Experience Has over 22 years experience providing services to the nuclear power industry, primarily as a Project Manager or Project Engineer. Extensive experience in managing

' or participating in independent assessments, technical reviews or program audits for large management and engineering programs such as piping and pipe supports, cable trays, equipment seismic qualification, integrated interaction, etc., to assure compliance with specific regulatory and licensing commitments or standard engineering practice.

Extensive experience in piping stress analysis including the development and/or use of several piping analysis computer codes and in-depth familiarity with ASME Section lil, p ANSI B31.1 and B31.7 code requirements. Developed and marketed two successful

( general purpose piping analysis programs (PIPESD and SRPIPE). Experience with development and use of finite element analysis computer codes for general structural analysis (NASTRAN, STARDYNE, ANSYS, STRUDL, SAP, etc.) with special emphasis on dynamic loadings (seismic, aircraft impact, soil-structure interaction, explosion, etc.).

! Exoerlence j i

May 1994 to Present: Programmatic Solutions,Inc., Smithtown, New York. Partner.

Seismic experience based operability evaluation of medium voltage switchgear for

Riverbend Station. Developed dynamic design guide for Limerick and Peach Bottom.

Seismic qualification of new instrument air station for Indian Point Unit 3. Organization l- and data collection for USl A-46 walkdown for Crystal River Unit 3.

1.990 to 1994: Robert L. Cloud & Associates, Inc., Berkeley, California. Senior Associate and Nuclear Services Business Manager.  ;

i Served as Project Manager and Lead Engineer for two separate programs at TVA's l Watts Bar and Sequoyah Nuclear Plants to establish and implement a design  !

, methodology and acceptance criteria for assuring stability of U Bolt supports. These '

t programs evaluated each individual U Bolt support used in conjunction with pinned behorterd . 7/94 l

IPROGRAMMATIC SOLUTIONS, INC. l D.H. RUTHERFORD Page 2 of 4 struts or snubbers in single or trapeze arrangements.

Served'as both Team Leader and participant in an integrated team approach (twelve reviewers from seven companies) that performed a detailed overview of the engineering plans and cost estimates for mechanical and civil / structural workscopes for completion of the Bellefonte Nuclear Plant Units 1 and 2.

Project Manager for the Engineering Overview Program which provided on-line review of activities at Watts Bar Unit 1 to assure proper implementation of improved methodologies for 18 elements of the Civil / Seismic Validation Program. Activities included establishing criteria and positions to resolve technical problems and licensing Issues. Project related tasks included participation in in-depth audits and technical reviews of engineering programs for piping and pipe supports, suspended systems (cable trays, conduit and HVAC), equipment seismic qualification, and integrated interaction. Also responsible for preparation /presentationof executive summary reports and interaction with client's upper level management.

Presenter / participant in Seismic Experience Methods Training Session for Seismic Verification of Equipment (SQUG methods) provided to engineers from Gilbert l Commonwealth, General Public Utilities Nuclear, Rochester Gas & Electric and Public

. Service Electric & Gas.

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! 1982 to 1990: EDAC GmbH, Frankfurt, Germany. President, part owner and Manager of Engineering Services. Responsibilities included all marketing, business development, and financial operations for small engineering consulting company specializing in

structural mechanics and dynamics. Clients were European and primarily German l speaking.

Project Manager responsible for the pre- and post test piping analyses and the

comparisons to test results for the client's (Siemens/KWU) representative support i configuration for the SHAG (seismic loading simulated by building vibration) and SHAM l (seismic loading simulated by direct actuation of the piping system) tests at a i decommissioned German test reactor (HDR facility). These were full scale, in-situ tests jointly sponsored by industry (EPRI, Siemens/KWU and others) and nuclear regulatory agencies (U. S. NRC and German TUEV). The relative ability of six different support configurations using struts, snubbers, limit stops and two different energy absorber designs to protect piping under seismic or dynamic loading was investigated.

Developed and marketed SRPIPE, an IBM PC-based computer program for the static,

' dynamic, thermal and stress analysis of piping systems. SRPIPE became one of the primary piping analysis tools for several European chemical companies (BASF AG, Linde AG, Voest/ Alpine AG, NSQ-Hauk GMBH, TUEV/Essen, and others).

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IPROGRAhiAfATIC SOLUTIONS, INC. I i D.H. RUTHERFORD Page 3 of 4 l Project Manager or Lead Engineer on several projects involving analyses of large and

, small bore piping systems (Main Steam, Feedwater, Auxiliary Cooling Water, etc.) for l Siemens/KWU nuclear plants (Biblis, Isar, Kruemmel, Philipsburg, etc.l. These analyses

! covered the gamut from standard static and dynamic (both response spectrum and time

! history analyses) load cases to special faulted conditions and nonlinear analyses such as pipe rupture, water / steam hammer, aircraft impact and explosion loadings.

j Performed independent confirmatory analyses of the reactor building of the Grafenrheinfeld Nuclear Plant under aircraft impact loading. Generated a composite l

model of the reinforced concrete outer shell, steel containment and reactor internals  !

i using axisymmetric solid and shell elements. Evaluated the effects of prescribed 0.07 sec. duration aircraft impact loading at 6 critical points of impact and compared final i results with results obtained using a separate computer code and procedure.

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1975 to 1981: Engineering Decision Analysis Company,Inc., Palo Alto, California and j Frankfurt Germany. Senior Project Engineer and later Principal. Primary responsibilities

included establishment and management of branch office in Germany.

Project Manager for a 5 man,18 month effort to perform seismic Soil Pile-Structure interaction analyses for the reactor building and other buildings for the pile foundation

sites at Angra Units 2 and 3 in Brazil for Siemens/KWU AG. Evaluations included deteimination of plie to-pile interaction effects, distribution of forces along the piles, building r9sponse to seismic loading and generation of secondary floor response spectra for subsequent equipment and piping analyses.

On site Project Manager for the independent review of analyses of the civil struetures, equipment and components of the Bushehr Nuclear Plant Units 1 & 2 (Iran) for Siemens/KWU AG. Responsible for work (4 engineers) performed on-site at KWU offices in Offenbach and Erlangen Germany, for coordination of independent check analyses performed by EDAC engineers in Palo Alto, and for monthly progress reports to KWU management. The objective of EDAC's 8+ man-year review effort was to provide assurance that all analysis procedures, methodologies, acceptance criteria and practices used by the German A/E met or exceeded equivalent codes and standards applicable to U.S. plants (ASME Code, Standard Review Plan, NRC Regulations, ANSI Standards, PVRC Gijidelines, etc.).

1972 to 1975: URS/ John A. Blume & Associates, San Francisco, California. Senior Engineer.

Project Engineer responsible for development of the PIPESD computer program, a joint u venture of JAB and Control Data Corporation (CDC) which provided static, thermal,

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5 l PROGRAMMATIC SOLUTIONS, INC. l

, D.H. RUTHERFORD l Page 4 of 4

( dynamic and stress analysis capabilities for nuclear and process piping systems. Wrote and maintained software, provided user support, and conducted seminars and workshops on the application of the program. The program was available through CDC Service Centers in the U. S. and Europe and successfully captured a large share of the i

piping analysis market.

1969 to 1972: Itek Corporation, Lexington Massachusetts. Structural Engineer.

Performed structural evaluations of various optical components of orbital telescopes using data center based computer codes such as STARDYNE, NASTRAN, ANSYS and

STRUDL. Investigated alternative supporting structures for a large (1.5 meter diameter) optical mirror. Developed a finite element based comp, uter program for performing analyses of axisymmetric structures under non-ax', symmetric loadings.

i Bagent Publications i Rutherford, D.H., and Bitner, J.L., " Stability of Pipe Supports Utilizing U-Bolts,"

i presented at ASME Pressure Vessel and Piping Conference, Minneapolis, June 1994;

.i published ASME PVP-Vol. 283.

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CHARBEL M. ABOU-JAOUDE

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' EXpMRTIRN Mr. Abou-Jaoude la a Technial Services Manager in VECTRA's Civil / Structural group, l with a broad technical and managerial experience in the power industry. His areas of j technical expertise are Structural Mechanics and Seismic Design; he has an in-depth ' i

! knowledge of various industry c xies/ standards such as Sections ill & XI of the ASME l Code, ANSI B31.1, IEEE-344 and 382, various USNRC Reg. Guides and - NUREG -  ;

l i Reports, ;WRC Bulletins, AISC, and ACI-34g. He is well versed in the' Generic i i

i implemeritation Procedure developed by the Seismic Qualification Utility Group for the i resolution of USI-A-46, and the methodologies developed by the industry for the response to Generic Letter 88 20 as outilned in NUREG-1407; he has completed the l-SQUG/EPRI sponsored A-46 and Seismic IPEEE training courses and has participated

in several A 48/IPEEE walkdowns as an SRT member. While at VECTRA, he has lead

the engineering efforts of various work scopes; his responsibilities have included:

j Criteria development, training and personnel development, project execution, interface j with regulators and outside organizations, and overall project management.

Currently; Mr. Abou-Jaoude is the Project Engineer for the NUSCo (Connecticut i Yankee, Millstone Units 1&2), and PSE&G (Salem 1&2) A-46 projects. He is also the Project Engineer for the PECo (Peach Bottom 2&3) IPEEE/A-46 project and an SRT l

member of the Wolf Creek and Limerick 1&2 IPEEE efforts. At Connecticut Yankee, l Mr. Abou-Jaoude has been instrumentalin the successful completion of the project; he has provided cost effective resolutions to a number of outliers, and lead the j development of implementation procedures for the procurement of new and l replacement equipment. l Mr. Abou-Jaoude was the Assistant Project Manager for the Civil / Structural effort at TU

Electric CPSES Unit 2 Project. He had primary management responsibility for the work i of 80 engineers in the Electrical Raceways, Seismic Equipment Qualification, and l I

l Seismic 11/1 disciplines. This effort involved the design validation of existing Raceway designs, issuance of new designs, establishing the qualification basis of all BOP Seismic _ Cat 1 and NSSS C1E equipment, procurement of new and replacement equipment, structural evaluation of non seismic commodities using an A-46 walkdown l based approach, and field engineering to support the completion and start-up of Unit 2. l l

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CHARBEL M. ABOU-JAOUDE Page Two

' pYDERTIRE (Cont'd) _

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Prior to his Unit 2 assignment at CPSES Mr. Abou-Jaoude was the Assistant Project- -l i

Manager for the Secondary Water Chemistry improvement Project at Consumers  !

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j" Power (Palisades). This project involved modifications to the existing blowdown l system, the addition of various equipment items,: and the installation of. 2000.ft. of (

piping., The design effort was completed in a period of six months with a peak staff of l 40. engineers; the design has been successfully implemented and its operation has

.provided improvements beyond the plant's initial expectations. In addition to this

. project he was involved in a number of projects for Consumers Power: He was the

[ - Project Engineer for consulting work related to the resolution of 79-14 piping and pipe l

support issues; he also was the Project Engineer for a modification to install a reactor

! head shielding which involved generating the amplified response spectra and

! performing the seismic analysis and qualification of the lifting ring / shielding structure.

Mr. Abou-Jaoude has also worked on a number of piping and equipment qualification

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projects for Commonwealth Edison and Northern States Power. He was the Project Engineer for the development of criteria to evaluate integral welded attachments for Prairie Island; the completion of this effort provided successful closure of an NRC 7g-14 issus.

l-l Previously Mr. Abou-Jaoude lead a group of 18 engineers, working on the seismic qualification of BOP components, in support of a successful SQRT audit for TU Electric's Comanche Peak Station Unit 1. He was responsible for the technical j adequacy, budget and schedule of the following scope:

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• Preparation of summary packages and supporting calculations to demonstrate

! th,e seismic qualification of storage tanks, heat exchangers, pumps, valves, the

!! diesel generator set, piping, and other electrical components (motors, battery racks, control panels, and instrumentation devices).

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• Evaluation of mechanical equipment rerating, under Section XI of the ASME s

,' Code, for revised design conditions such as pressures, temperatures, nozzle ,

loads, and or acceleration values (approx. 200. stress reports).

' Mr. Abou-Jaoude was also involved in the Comanche Peak cable tray hanger design validation effort. He was a group lead responsible for qualifying cable tray systems.

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7 VECTRA CHARBEL M. ABOU-JAOUDE Page Three s

[ EXPERTISE (Cont'd) 4 This required detailed dynamic analysis and evaluation of structural members and anchorages. He was involved in the development of criteria for modification reduction

. techniques. He also worked on the dynamic testing of full scale cable tray systems and provided analytical results for correlation with measured test data.  !

Prior to joining VECTRA, Mr. Abou-Jaoude has worked in the Middle-East on the construction of several commercial and industrial reinforced concrete buildings. He has also worked as a field engineer responsible for the Installation and maintenance of i equipment at an automotive refurbishing plant in the United Arab Emirates.

EDUCATION ,

O M.S., Civil Engineering, December 1985 University;of Michigan Ann Arbor, Michigan B.E., Mechanical Engineering, July 1984 American University of Beirut. Box 110236, Beirut, Lebanon i

I PROFESSIONAL AFFILIATIONS American Society of Civil Engineers l

American Society of Mechanical Engineers

Tau Beta Pi Honor Society

Chi Epsilgn Honor Society

. PUBLICATIONS Lee, B. J.~, Abou-Jaoude, C. M., and De Estrada, M., " Issues of Control Panel Rigidity in Selsmic Qualification," Proc. of 1991 Pressure Vessels and Piping (PVP) Conference, i Vol. 220. -

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T VECTRA CHARBEL M. ABOU JAOUDE Page Four a

PUBLICATIONS (Con't) i Lee, B. J., and Abou-Jaoude, C. M., "Effect of Base Uplift on Dynamic Response of Electrical and Mechanical Equipment," Proc. of 1992 Pressure Vessels and Piping

- (PVP) Conference, Vol. 237-2.

Roche, T.R., Abou-Jaoude, C.M., et al, " Comparison Between Analytical and Test Results for Transformer Base Details," Proc. of 1993 Pressure Vessels and Piping (PVP) Conference, Vol. 256-2. .

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APPENDIX B: Composite Safe Shutdown Equipment List (Crystal River Unit 3) 15-Dec-95 SEQ T CL ID NO EQUIP DESCRIPTION DRAWINC KDC/ EVAL SSEL NOTE NOEL 4/ P%R - SUPORT DW ' INTERCONS R

N EL DEstRED 14 ACDP45 DIESEL ROOM 480 VOLT 206 443-2 DIESEL S IN USE Y MTMC4 560 DISTRIBUTION PANEL 3A 119 IN USE 14 *ACDP46 DIESEL ROOM 480 VOLT 206-043-2 DIESEL S IN USE Y MTMC-5 561 DISTRIBUTION PANEL 3B I19 IN USE ACDP-51 CONTROLCOMPLEX 206443 CONTROL 5 ON Y MTMC-3 IBL 650 A 14 DISTRIBUnON PANEL A 145 ON ACDP-51-T CONTROL COMPLEX 206 443 CON 110L 5 .ON N NOhT 598 A 4 DISTRIBUDON PANEL A 124 ON TRANSFOILAIER ACDP-52 CONTROLCOMPLEX 206443 CONTROL S ON Y MTMC45AR 651 B 14 DISTRIBUTION PANEL B 145 ON ACDP-52-T CONTROLCOMPLEX 206 443 CONTROL S ON N NONE 599 B 4 DISTRIBUTION PANEL B 124 ON TRANSFORMER CONTROL ON .Y MntC-7 2AR 600 X 14 ACDP-68 ES DISTRIBUTION PANEL 3AB 206 4 43 S 124 ON ACDP48-T ES DISTRIBUTION PANEL 3AB 206443 CONTROL ON N NONE 469 X 4 S TRANSFORMER 124 ON 8B All433-ASV AllD l AllD-ID, AIID-2,& AHD- CONTROL S N CC AIR i 248 3 CONTROL 164 8B All433-Sv Alto-l. AllD 1D, AHD-2,& AllD- All-90 CONTROL 5 Y ACDP483 249 3 CONTROL 164

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SEQ T CL ID NO EQUlr DESCRIFTION DitAWING BLDGf EVAL SSEL NOTE NORMt FWR styORT DW LNTERCONS g n mm 270 8B Mi-194-SV AHD 13 & AHD-14 CONTROL AH86 CONTROL S Y MTMC-4 2B 164 271 8B AH-195-SV AHD 15 & AHD 16 CONTROL AHt7 CONTROL S Y N 164 3EN 720 10 AH-l% AHD-I CONTROL CONTROL S CC AIR

.POSI 160 721 10 AH-l% AHD-2 CONTROL CONTROL S- CC AIR POS2 gog 722 10 Mi-l% AHD-3 CONTROL CONTROL s CC AIR POS3 164 723 10 AH-196- AHD 1D CONTROL AUXILIARY s CC AIR POS4 160 245 8B AH-l%5V AHD 1, AHD-ID. AHD-2,& AHD. AH90 CONTROL S Y- ACDP483 3 CONTROL 164 246 BB AH-199-SV AHD 4 & AHD-5 CONTROL AH80 CONTROL s Y MTMC-4 4B 164 272 8B AH-200-SV AHD4 & AHD-7 CONTROL AH81 CONTROL s Y MTMC43D 164 247 8B AH-246-SV AHD-12 CONTROL AH-89 CONTROL s Y ACDP483 164 135 8B AH-250-SV AHD-87 & AHD-22 POST- Al!88 AUXIUARY s Y ACDP483 ACCIDENT CONTROL gg9 145 8B AH-310-SV AHD47 CONTROL All26 AUXIUARY S Y MTMC-3 98 119 146 8B All-3 t l-SV AHD-88 CONTROL All27 AUXILIARY .s Y MEMT-5 2B 119 Appendix B 2

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!19 307 SB AH-3564V AHD43 CONTROL AH75 DIESEL s .- Y- MTMC42D 119 i t

30g .8B AH-3574V AHD41 CONTROL AH74 DIESEL s Y- MTMC42C i19 3 04) SB AH-3584V AHD42 CONTROL AH75 DtESEL s Y MDO42D I19 302 8B- AH-3654V AHD40 CON 11tOL AH77 DIESEL s Y MIMC-22 119 2M

-303 8B AH 366 SV AHD40 CONTROL AH78 DIESEL s Y MTMC 5 2D 119 304 8B AH-367-SV AHD-58 CONTROL AH77 DIESEL s Y MTMC-22 11, 2m 305 8B AH-3684V AHD-59 CONTROL AH78 DIESEL s Y MTMC-5 2D '

' i19 250 88 AH-381-ASV AHD-l. AHD-ID, AHD-2,& AHD- -CONTROL s N. CC AIR 3 CONTROL 164

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251 8B AH-3814V AH90 CONTROL 3 Y ACDP483 3 CONTROL 164 '

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763 12 AH-506-PS AHP-I A & AHP-1B CONTROL AHI48 CONTROL s Y MTMC-21 164 SCER 764 12 AH-508-PS AHP-IC & AHP-1D CONTROL AH149 CONTROL S Y k N IAL 164 ,

266 8B AH-517-SV AH150 CONTROL 3 Y ' DPDP-5A21 164 -

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EL DESIRED N

8B AH-5184V AH150 CONTROL S Y SPSP-5B 21 267 164 252 8B AH448-ASV AHD-1, MID-ID, AHD-2, & AHD- CONTROL S Y 3 CONTROL 164 253 8B AH4484V AHD-l. AHD-ID, AHD-2,& AfD M190 CONTROL S Y ACDP483 3 CONTROL 164 8B AH449-ASV AHD-l. AHD-lD AHD-2,& AHD- CONTROL S N CC AIR 254 3 CONTROL 164 283 8B AH-9534V AHD-99 CONTROL AH90 COVTROL S Y ACDP483 164 262 8B AH-9664V AHD l CONTROL AH90 CONTROL S Y ACDP483 164 263 8B All-9674V MID-1 & AIID-1DCONTROL AH90 AUXILIARY S Y ACDP483 160 l

273 8B AH-968-SV AllD-2 CONTROL AH90 CONTROL _S Y ACDP483 164 255 8B AH-969-SV AHD-3 CONTROL All-90 CONTROL S Y ACDP483 164 274 8B AH-970-SV AHD-99 CONTROL AH90 CONDtOL S Y ACDP483 164 212 8B AH-971-SV AHD-12 CONTROL AH89 CONTROL S Y ACDP483 108 718 20 AliCP-4 SCR CABINET FOR AlliiE-4A CONTROL S N/A N AND AllHE-4B 164 N/A I

10 AHD-01 CONTROL COhlPLEX E!AKE-UP 302-753-1 CONTROL S OPEN CC AIR 278 AIR 164 OPEN Appendix B 4 m - __ ___ ._. - _ _ . _ _ _ _ _ _ _ - _ _ . _ _ _ _ _ _ _ _ _ _ _

. . . _ _ . _ _ . _ _ __ - __-_._.._______.__.m O O c san T CL ID NO EQUIP DESCRIFFION DRAWING BLDGf EVAL SSEL NOTE NORM PHlR SUPORT DW INTERCONS R

3 EL naamrm 237 10 AHD41D CONDOLCOMPLEX MAKF UP 302-753-1 AUXILLARY s CC AIR AIR 160 260 10 AHDO2 PNEUMATIC RF11FFTO 302-753-1 CONTROL 5 CC AIR ATMOSPHERE 164 242 10 AHD43 CONTROLCOMPLEX FANS 302-751-1 CONTROL s CCAIR INTAKE gg 261 A 10 AHD44 AHF-17A INTAKE 302-753-1 CONTROL s OPEN Y. MnC44E AH80 lH OPEN CC AIR i

277 A 10 AHDOS AHF-17A DISCHARGE AH30,302- CONTROL s OPEN Y MDdC-4 4R i 753-1 164 OPEN CC AIR 275 B 10 AHD46 AHF-17B INTAKE All81,302- CONTROL s OPEN Y MNC4 3D, 753-1 IM OPEN CCAIR 288 B 10 AHD07 AHF-17B DISCHARGE AH81,302- CONTROL s OPEN Y MTMC4 3D, 753-1 3 r0 OPEN CC AIR AHD-12 AH89,302- CONTROL s OPEN Y ACDP483, 211 X 10 SUPPLY TO CHEMLAB CC AIR 753-1 108 OPEN 243 A 10 AHD-13 AHF-19A INTAKE AH86,302 CONTROL S OPEN Y MDC42E 753-1 164 OPEN CCAIR 258 A 10 AHD-14 AHF-19A DISCHARGE AHf6,302- CONTROL S OPEN Y MThC42E 753-1 IH OPEN CC AIR l

AHD-15 AHF-19B INTAKE AH87. 302- CONTROL s OPEN Y MTMC-22 244 B 10 753-1 IM OPEN 3KN.CC AIR AllD-16 AHF-19B DISCHARGE All87. 302- CONTROL s OPEN Y MTMC-22 259 B 10 753-1 164 OPEN 3KN,CC AIR Appendix B 5

~.

i.) U d SEQ T CL ID NO EQL,tr DESCRIPHON DRAWINC BLDCI EVAL SSEL NOTE NORM / PWR SUPORT DW INTERCONS DESIRED

[ EL AHD-17 95* EXIVATION RETURN AH88,302 CONTROL OPEN Y ACDP483..

196 X 10 S CC M 753-1 103 OPEN SECONTARY PLANTIAB HOOD AHas,302- CONTROL OPEN Y ACDP483 197 X 10 AHD-22 S NM SUPPLY 753-1 104 OPEN AHF-22C DISCHARGE AH77,301- DIESEL S C WSED Y MTMC-22 325 B 10 *AHD-58 754-1 124 OPEN 2E EDO STARTAIR i

AHD-59 AHF-22D DISCHARGE AH78,302- DIESEL S C1DSED Y MTMC-5 2D, 320 B 10 754-1 120 OPEN EDO START AIR AHD40 EGDG-1B INTER-ROOM AH77. AH78 DIESEL S C WSED Y MTMC-22 324 B 10 302-754-1 124 OPEN 2W OR MIMC-5 2D, EDG START AIR i AHD41 AHF-22A DISCHARGE AH74,302 DIESEL C WSED Y MTMC-4 2C, 321 A 10 S 754-1 124 OPEN EDO START ,

AIR

^

AHD42 AHF-22B DISCIIARGE AH75,302- DIE EL CWSED Y MTMC-4 2D.

322 A 10 S 754-1 124 OPEN. EDO START AIR AHD43 EGDG IAINTER-ROOM AH74, AH75 DIESEL C WSED Y MTMC-4 2C f 323 A 10 S 302-754-1 124 OPEN OR N  ;

2D, EDO STARTAIR 191 A 10 AHD-87 AHF-8A DISCHARGE AH26,302- AUX 113ARY S OPEN Y MTMC-3 9B.

751-1 128 OPEN IAAIR 10 AHD-88 AliF-8B DISCIIARGE All27,302- AUX 111ARY S OPEN Y MTMC-5 2B, 187 B 75l-1 124 OPEN IA AIR i l

Appendix B 6

~. -

seq T CL ~ ID No . EQUIF DESCRIFTION DRAWING BLDCI EVAL SEEL NOTE NORMI PWR SUPORTIpW INTERCONS R

3-g EI, pm 276 X 10 AHD 99 VENTIllATKW EQUIPMENT 302-753-1 CONTROL g OPEN Y' CCAIR ROOM SUPPLY AIR IM OPEN ,.

268 A 21 ANDR-IA CommtOLCOMPLZX HVAC AHI48 CONTROL g ON Y m3137 COMPRESSED AIR DRYER A iM ON >

AHI49 ON Y~

269 B 21. - AHDR-IB CONTROLCOMPIIX HVAC WMPRESSED AIR DRYER B CONTROL S ACDP-5237 IM ON 642 A- 9 AHF-OlA REACTOR BUILDING AIR AH28,302- REACTOR 3 FAST Y MTMC 4 IB HANDUNO FAN A 751-1 1M FAST 500 B 9 AHF4tB REACTOR BUllDING Alst AH29,302- REACTOR g FAST Y MTMC HANDID.O FAN B 751-1 103 FAST 6AN 501 AB 9 AHF-Olc REACTOR BUIIDING AIR AH30,302- REACTOR S FAST Y MTMC-71B HANDUNG FAN C 751-7 103 FAST 147 A 10 AHF48A SPENT WELNW PUMP A AH26,302- AUXILLARY S ON Y MTMC-3 9B i AIR HANDUNG 751-1 '

119 ON 148 B 10 AHF-OSB SPENT FUELCOOIANT PUMP B AH27,302 AUXIUARY S ON Y MTMC-5 2B AIR HANDUNG 751-1  !!9 ON 256 A 9 AHF-17A CONTROLCOMPLEX NORMAL AH30,302- CONTROL S ON Y MTMC44B SUPPLY FAN A 753-I IH ON 9 AHF-17B COVTROLCOMPLEX NORMAL AHSI,302- CONTROL ON Y MTMC4 3D 264 B S SUPPLY FAN B 753-1 IH ON AHF-19A CONTROLCOMPLIX RE1 URN AH86,302- CONTROL ON Y MTMC42B 257 A 9 S FAN A 753-1 164 ON l

9 AHF-898 CONTROLCOMPLEX RETURN AH87,302- CONTROL S ON Y MTMC-22 265 B FAN B 753-1 164 ,, ON 3U  !

- Appendix B 7 l

l

(-. .

d ( U SEQ T CL ID NO EQUlr DESCRIFTION DRAWING BIEGf EVAL SSEL NOTE NORM / PWR SLTORT DW INTERCONS R-N EL DESIRED 318 A 9 m-22A DIESELGENERATOR ROOM A AH74,302- DIESEL $ M Y MD4C-4 2C SUPPLY 754-1 137 ON 326 A 9 m-22B DIESELGENERATOR ROOM A AH75,302- DIESEL S M Y KndC-4 2D SUPPLY 754-1 131 ON 329 B 9 AHF-22C DIESELGENERATOR ROOM B AH77,302- DIESEL S OFF Y m SUPPLY 754-1 137 ON 2G 327 B 9 AHF-22D DIESELOENERATOR ROOM B AH78,302- DIESEL S Of7 Y MTWC-5 2D SUPPLY 754-1 131 ON AHF-54A EFIC ROOMS COOLING A AHit7. 302- CONTROL ON Y MTMC-21 219 A 10 S 765-1 124 ON 3E 220 B 10 AHF-54B EFIC ROOMS COOLING B AHis6,302- CONTROL S ON Y MTMC-22 765-1 124 ON 3U AHHE44A HENI1NG UNIT A FOR CONTROL ON Y MTSW-3J 287 X 10 AHII8,302- S 2C, AHCP-4 CONTROLCOMPLEX 753-1 170 ON AHHE44B HEATING UNIT B FOR AH120,302- CONTROL ON Y MTSW-3J 290 X 10 S 3C,AHCP4 CONTROLCOMPLEX 753-1 170 ON AHHF-0$A COOllhG UNIT A FOR 302-753-1 CONTROL IN USE N CHP-lA 286 A 10 S CONTROLCOMPLEX 302-756-1 170 IN USE AHHE-05B COOllNG UNIT B FOR 302-753-1 CONTROL S IN USE N CHP-1B 289 B 10 CONTROLCOMPLEX 302-756-1 170 IN LEE 21 AIIHE-13A COOLING COILS FOR REACTOR 302-756-1 INTER s ON N N/A NObT 333 BUILDING PENETRATIONS A 095 AfillE-13B COOLING ColLS FOR REACTOR 302-756-1 INTER S ON N N/A NONE 334 21 BUIDLING PENETRATION B 093 , , ,

Appendix B . 8

~

,m m -,

Sze T CL ID No EQUlf DESCRIFFION DRAWING BLDGf EVAL SSEL NOTE NORW PWR SUPORT DW INTERCONS R

N EL DESIRED 10 AHHE-29A COOUNG UNIT FOR SFP-IA 302-751-1 AUXILIARY S IN USE N SW 149 119 IN USE 150 10 AHHE-29B COOUNO UNIT FOR SFP-1B 302 75I-1 AUXILLARY S IN USE N SW l19 IN USE 76 21 AHHE-30A COOUNG UNIT FOR DCP-1A 302-751-1 AUXIUARY S IDII N N/A 095 IN USE 77 21 AHHE-30B COOUNG UNIT FOR DCP-1B 302-751-1 AUXIUARY S IDLE N N/A 095 IN USE 643 X 10 AHHE-31A COOUNG UNIT A FOR 302-751-1 REACTOR S IN USE N AHF-IA SW NN 126 IN USE M CI AHHE-31B COOUNG UNIT B FOR REACFOR IN USE N AHF-1B,5W 644 X 10 302-751-1 S OR O REACTOR BUILDING 126 IN USE AHHL3tc COOUNG UNITC FOR 302-751-1 REACTOR IN USE N AHF-IC, SW 502 X 10 S OR Q REACTOR BUIU)ING 103 IN USE AHHE-32A h10TORCOOLER FOR AHF-IA REACFOR IN USE N SW OR Q 645 X 10 302-751-1 S 126 IN USE AHHE-32B hf0 TOR COOIIR FOR AHF-1B 302-751-1 REACFOR IN USE N SWOR Q 503 X 10 S 103 IN USE AHHE-32C hf0 TOR COOLER FOR AHF-IC 302-75l-1 REACTOR IN USE N SW OR O 504 X 10 S 103 IN USE AHHE-43 COOllNG UNIT A FOR EFIC 302-765-1 CONTROL 5 IN USE N CHP-I A OR 217 A 10 CHP-1B ROOhlS 124 IN USE AHHE4 COOUNG UNIT B FOR EFIC 302-765-1 CONTROL S IN USE .N CHP-1 A OR -

218 B 10 ROOklS .

IN USE CHP-1B 124 s

AIIP41A CONTROL COkiPLEX ilVAC AIR AHl48 CONTROL 5 ON Y KgThtC-21 279 A 12 SCER COhiPRESSOR A 164 -

ON Appendix B 9 h _ _ . - _ - - - _ - - - _ _ _ _ _ _ _ _ _ . - . _ _ _ _ _

p ,

s V Oe, seq T CL ID NO EQUIP DESCRIFTM DRAWING BLDGf EVAL . SSELNOTE NOR1W PWR SUPORT DW INTERCONS R

N EL DESIRED CONTROL COMPilX HVAC AIR AHI48 COtmtOL ON Y MTMC-21 280 A 12 - AHP-OlB S SCER COMPRESSOR B 164 ON 281 B 12 AHP-01C CONTROLCOMPIIX HVAC AIR AH149 CONTROL S ON Y MTMC4IAL COMPRESSOR 164 ON CONTROLCOMPIIX HVAC AIR AH149 CONTROL ON Y MTMC4IAL 282 B 12

• AHP41D COMPRESSOR D S

164 ON 719 20 hl PANEL COfmtOL S 164 e

8A ARV-48 VACUUM BREAKER BFIIFF 302-131-1, TURBINE g C1DSED Y DPDP-3B 2,23

1. 2 FOR CDHE-4A AR-10 119 OPEN 465 8A ARV-49 VACUUM BREAMR nriIFF 302-131-1, 1URBINE S CIDSED Y DPDP-3A FOR CDHE-4B AR-li 27,30 127 OPEN 342 B 8A ASV-005 EFTB-1 STEAM ADMISSION AS01,302- INTER S CIDSED Y DPor.8B 5 &

051-1 095 OPEN 6 731 X 0 ASV-050 EFTB-1 TRIP & THROTTTE 302-051-1 INTER S OPEN N EFTB-l 095 CONTROL OOVE N ,

875 N/A N/A ASV-079 MSDT-20 ISOLATION 302 451-1 INTER N OPEN N N/A 119 CLOSED ,

881 N/A N/A ASV os0 MSDT-191SOLAllON 302451-1 INTER N OPEN N N/A 124 CLOSED 847 N/A N/A ASVOs9 ASDT-121 SOLATION 3024511 INTER N OPEN N N/A 095 CLDSED 848 N/A N/A ASV-090 ASDT-13 tSOLATION 302-051-1 INTER N OPEN N N/A 095 CIDSED 849 N/A N/A ASV-091 ASDT-I4 ISOLATION 302-051-1 INTER N OPEN N N/A 095 CLOSED Appendix B 10

N wY O SEQ T CL IDNO EQUIP DESCRIPTION DRAWING BLDGf EVAL SSEL NOTE NORMt Pwit SUPORT DW INTERCONS R

N. EL DESIRED N/A ASV492 ASDT-l5 ISOIADON 30245l-1 IN11R N OPEN N N/A 850 N/A 095 CwSED ASDT-16 ISOLATION 302451-1 INTER N OPEN N N/A 844 N/A N/A - ASV-157 095 CLOSED 8;5 N/A N/A ASV-160 ASDT-lS ISOLATION 302451-1 IMER N OPEN N N/A 095 CwSED N/A ASV-163 ASDT-171SOIADON 302-051-1 INTER N OPEN N N/A 846 N/A 095 CIDSED 869 N/A N/A ASV-169 ASDT-13 ISOLATION 302-051-1 INTER N OPEN N N/A 100 C wSED 341 A 8A ASV-204 EFTB-I STEAM ADMISSION 302451-1 INTER S CLOSED Y DPDP-SA 15 095 OPEN A I7 20 ATCP-l ANTICIPATED TRANSIENT CO!GROL S N/A N 601

%TT110UT SCRAM LOGIC 124 N/A CABINET BSP-IA REACTOR BUILDINO SPRAY 302431-1 AUXILLARY S OFT N N/A NONE 2 5 PUMP A 075 oft BSP-1B REACTOR BUILDING SPRAY 302431-2 AUXILIARY S OFT N N/A NONE 3 5 PUMPB 075 OFT 132 19 CA-10-TE BOTTOM BORIC ACID 302471-1 AUXILLARY S IN USE Y hWI-X OR STORAGE TANK CAT-5A i19 IN USE NNI-Y 130 A 1g CA-11-LT BORIC ACID STORAGE TANK A 302 4 71-1 AUXILIARY S IN USE Y VBDP-18 OR I19 IN USE VBDP-3 25 CA-12-TE DOTTOM BORIC ACIT 302471-1 AUXILIARY S IN USE Y NN1-X OR 133 19 STORAGE TANK CAT-3B 119 IN USE NNI-Y I

l Appendix B ll n-- - . - - - - _ - - - - _ - - - - - - - - - - - - - - - - - - - - - _ - - - _ _ _

r3 p f~~.

SEQ T CL ID NO EQUIP DESCRIPTION DRA%1NG BLDGI EVAL SSEL NOTE NORM / PWR SUPORT DW INTERCONS R

N EL DES 8 RED s

CA 13-LT BORIC ACID STORAGE TANK B 302471-1 AUXIUARY S IN USE Y VHDP-18 OR 13i B 18 VBDP-3 25 119 IN USE 21 CAHE-1 PRESSURIZER SAMPi E COOER 302401-4 AUXILLARY S IDE N SW 19 'X 095 IDE CAdE-2A S1 TAM OENERAIDR ASAMPE 302401-4 AUXIUARY IDLE N SW 20 X 21 S

. COOER 095 IDLE 21 CAHE-2B STEAM OENERATOR B SAMPE 302401 4 AUXIUARY S IDE N SW-21 COOER 095 IDE CAHE-5 PASS RC SAMPLE COOER 302-700-1 INTER S OFF N N/A NONE 351 21 095 OFT CAHE4 PASS DECAY HEAT SAMPE 302-700-1 AUXIUARY S OFT N N/A NONE-112 21 COOER 095 OFT CAHE PASS RC SAMPE PRE 400ER 302-700-1 INTER S OFT N N/A NONE 352 21 095 OFF CAP-IA BORIC ACID PUMP A CA01,302 AUXIUARY OFF Y MTMC-310B 128 A 5 S 671-1 gg9 og 129 B 5 CAP-1B BORIC ACID PUMP B CA01,302- AUXIUARY S OFF Y MTMC-5 4B 671-1 119 ON 134 A 21 CATSA BORIC ACIDSTORAGE A 3024 71-1 AUXILLARY S IN USE Y MTMC-310D 119 IN USE 144 B 21 CAT-5B BOR]C ACID STORAGE TANK B 302471-1 AUXIUARY S IN USE Y MTMC4ID 119 IN USE 8B CAV-002 PZR AND LETDOWN OUTSIDE 3024 72-1, INTER S CLOSED Y DPDP-5B 22 335 PENETRATION SAMPLE CA-16 095 OPEN ISOLABON Appendix B 12

_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ __ -- -_ + _ . _ _ _ _ _ -_ --

f~% f% rs N

l sEO T CL ID NO EQUIP DESCRIFTKW DRAWI.% BLDGf EVAL- SSELNOTE NORW PWR SUPORT DW MTENCOME R

y EL Des.arn 7 CAV-057 BORIC ACID FUMPTD MAKE4JP CA22,302 AUXRIARY S

"" Y ACDP-514, 155 A~

' TANK 671-1 119' OPEN IA 158 A '8B CAV457-sV CAV-57 CONTROL - CA22 AUXILIARY S Y ACDP-514 119 179 B 7 CAV460 BORIC ACID PUMP TO MAAFAJP CA22,302- AUXIUARY S CIDSED Y ACDP-32 5

. TANK 671-1 121 OPEN IA 159 B 8B CAV4605V CAV40 CONTROL CA22 AUXIUARY S Y- ACDP-52 5 119 489 8A CAV-126 RC LETDOWN SAMPLE INSIDE 302-672-1 REACTOR S CLOSED Y MTMC-4 9A PENETRATIONISOLATION CA-12, ES- 095 OPEN VALVE AS4 649 20 CCBT CENTRAL CONDtOL BOARD CONTROL S N/A N TERMINATION CABINET I45 N/A 461 18 CD467-LTI CONDENSATE STORAGETANK 302-011-2 TURBINE $ IN USE Y VIRDP-l l OR LEVEL 339 IN USE VBDP-511 444 Ig CD-10H.T CONPENSER CDHE-4A 302-101-1 TURBINE S IN USE Y NNI Ho"AT.LL EVEL 095 IN USE 445 Ig CD-101-LT . CONDENSERCDHE4B 302-101-1 TURBINE S IN USE Y NNI HOlvELLEVEL 095 IN USE 734 21 CDHE-4A MAIN CONDENSER A 302-101-1 TURBINE S IN USE N N/A 095 IN USE 735 21 CDHE4B MAIN CONDENSER B 302-101 1 TURBINE S IN USE N N/A 095 IN USE 439 6 CDP-IA CONDENSATE PUMP A 302-101-2 TURBINE S ON- N N/A 095 oft ,

Appendix B B

7-s . %  %

sEn Y CL inNO EQUlF DESCRIFDON pgAwmc BIAGf EVAL SSEL NOTE NORM PWR SUPORT DW INTERCONS R

N EL wem 6 CDP-1B CONDENSATE PUMP B 302-101-2 TURBINE S ON N 447 095 OIT 302411-2 g N USE N N/A 466 X 21 CDT-1 CONDENSATE STORAOE TMK WEKF BER I19 IN USE CONDENSATE STORAGE TANK 3024 11-2 CIDSED N N/A 880 X N/A CDV-103 WEST BER N TO EFW PUMPS ISOLATION 121 OPEN 886 0 CERJNO CONTROL ROOM CEILING CONDtOL I45 804 X 8A CFV-5 CORE FIDODTANK A CF01,302- REACTOR S OPEN Y MDec-76B DISCHAROE ISOIATKel 702-1 119 CIDSED 805 X 8A CFV4 CORE FIDOD TANK B CF02,302- REACTOR S OPEN Y MTMC-7 6C DISCHARGEISOLATION 702-1 119 CIDSED CH-378-PT CHV4s CONTROLOF CHHLIA NONE CONTROL 5 IN USE N CC AIR 239 A 1g 164 IN USE CH-379-PT CIIV49 CONTROLOF CHHLIB NONE CONTROL IN USE N CC AIR 241 B 18 S 164 IN USE CHHLIA CONTROLCOMPLEXCHILLER A CH01,302- CONTROL ON Y DPDP-5A 9 238 A 11 S 756-1 164 ON AND MTSW-3F3C CHHLIB CONTROL COMPLEX CHIL11.R B CH02,302- CONTROL 5 ON Y DPDP-5B 9 240 B 11 756-1 164 ON AND MTSW-303C 284 A 5 CHP-IA CillLLED WATER PUMP A CH03,302- CONTROL S ON Y MTMC-4 2A 756-1 164 ON o

CIIP-1B Cl!! LIED WATER PUMP B C1104,302- CONTROL ON Y MTMC-22 285 B 5 S 756-1 164 ON 4U Appendix B 14

t O O O l SEQ T CL ID NO EQUIP DESCRIPTION DRAWING BLDGI EVAL $$EL NOTE NORM / P%R SCPORT DW LNTERCONS

m D.....

IN USE N N/A 293 X 2i CHT-1 CHTII FD WATER EXPANSION 302-756-1 CONTROL s TM 181 IN USE -

CHV468 SERVICE WATERTO CHHLIA 302-756-1 CONTROL s N USE Y CC AIR 291 A 7 CONTROLVALVE 172 IN USE ,

761 7 CHV468- CHV48 COVTROL (NONE) CONTROL s IN USE N CC AIR

• POS 164 IN USE 292- B 7 CHV-069 SERVICE WATER TO CHHLIB 302-756-1 CONTROL s IN USE Y CC AIR CONTROL VALVE 172 IN USE 7 CHV469- CHV-69 CONTROL (NONE) CONTROL s N USE N CC AIR 762 POS 164 IN USE 8B CHV490 NORMALCOOIJNG TO AHHL CH07,302- CONTROL S OPEN Y VBDP-115 216 B 44 ISO!ATION VALVE 765-1 124 OPEN 222 B 8B CHV-097 APPX. R COOLING FROM AHHL CH07,302 CONTROL s CLOSED Y \DDP-11 $

44 ISOIATION VALVE 765-1 125 CLOSED CllV-100 CH07,302- CONTROL s IN USE Y CC AIR 22i B 7 AHHE-44 (EFIC ROOMS)

CONTROL VAL %E 765-1 125 . IN USE CHV-100- CHV-100 CONTROL 308494 CONTROL s IN USE CC AIR 755 7 POS 124 IN USE 8B CIIV-100-SV CHV-LOO CONTROL CH07 CONTROL S Y VBDP-11 $

213 B 124 CH07,302- OPEN Y VBDP-ll 5 l 214 B 8B' CHV-101 NORMAL COOLING FROM CONTROL s AnniL44 ISOLATION VALVE 765-I 124 OPEN 8B CHV-108 NORMAL COOUNG TO AHHL CH08,302- CONTROL s OPEN Y VBDP-314 224 A 43 ISOLATION VALVE 765-1 131 OPEN

[

Appendix B 15

,m (s em.

seq T CL I)No EQUIP DESCRIFLDN DRAWING BLDGI EVAL SSEL NOTE NORhu PWR SUFORT DW. INTERCONS R

N EL DESIRED CHV-ll3 CH08,302- CONTROL IN USE Y \1tDP-314, 223 A 7 AllHEA3(EFIC ROOMS) S C AIR CONTROLVALVE 765-1 130 IN USE 756 7 C H V-113- CHV-113 COVTROL 308-894 CONTROL S IN USE N CE AIR POS 124 N USE Y \1 BOP-314, 215 A 8B ' CHV-Il34V CHV-Il3 CONTROL CHOS W NTROL S CC M 124 70 A 18 DC45-FT DCP-I A DISCHARGE 302431-1 AUXILLARY S IN USE Y VBDP-21 OR 095 IN USE VBDP414 72 B 18 DC46-PT DCP-IB DISCHARGE PRESSURE 302431-2 AUXHJARY S IN USE Y VilDP-11 OR 095 IN USE VBDP-5 Il 18 DC-50-LT DC SURGETANK DCT-IAIIVEL 302431-1 AUXIIJARY S IN USE Y TPC 71 095 IN USE DC-54-LT DC SURGE TANK DCT-1B LEVEL 302431-2 AUXILLARY S IN USE Y TPC 75 18 095 IN USE DCl!E I A DECAY llEATCIDSED CYCLE ?92431-1 AUXILLARY IDLE N DCP-IA 45 A 21 S COOllNC A 095 IN USE DCifE-1B DECAY llEAT CIDSED CYCLE 302431-2 AUXILLARY S IDLE N DCP-1B 64 B 21 COOLING B 095 IN USE DCP-IA DECAY llEAT CIDSED CYCLE DC01,302- AUXILLARY OFF Y DPDP-5A 9 67 A 5 S COOLING PUMP A 631-1 095 ON AND WW-3F 74 B 5 DCP-IB DECAY llEAT CIDSED CYCLE DC02,302- AUXILLARY S OFF Y DPDP-5B 9 COOLING PUMP B ,

631-2 095 ON AND MTSW-3G DCT-1A DECAY IIEAT CCC SURGE 302431-1 AUXILIARY IN LSE N N'A 113 A 21 S' TANK A 095 IN USE Appendix B 16 m --- _ _

- - - = . _ _ - . - - -. . - . = _ _ ~ . . . . . . . . . . _ . - , - . .

73 .

m F

'see T CL ID NO EQUlf DESCRIFUON DRAWING BLDGI EVAL SSEL MFFE NORW FH1R SUPORTWUr INTERCONS h EL neuern DCT-1B DECAY HEATCCC SURGE 302431-2 AUXILLARY S IN USE N . N/A 114 B 21 TANK B 095 IN USE ,

1 726 7 DCV-IO6 NITROGEN SUPPLY TO DCT-1A 302431-1 AID 03JARY N OPEN N- WA  !

095 C1D8ED =

727 7 DCV-188 NITROGEN SUPPLY TO DCT-1B 302431-2 AUXILLARY N OPEN N N/A 095 C1D8ED 68 A 7 DCV-190 DCT-I A OVERPRESSURE 302431-1 AUXHlARY $ IN USE N N/A CONTROLVALVE 095 IN USE i

7 DCV-191 DCT-IB OVERFRESSURE 302 431-2 AUXILLARY IN USE N N/A 69 B S CONTROLVAVLE ~ 095 IN USE i DF-t-13 DIESELGENERATOR FUELOfL DF01,302- DIESEL IN USE N N/A 743 A 18 DAY TANK AIIVELSETICH 281-1 gg, IN USE i DIESELGENERATOR FUELOIL DF01,302- DIESEL IN USE N N/A 744 A 18 DF-2-13 DAY TANK ALEVEL5%TFCH 281-1 119 IN USE 745 B 18 DF-3-LS DIESEL GENERATOR FUELOIL DF02,302- DIESEL IN USE ~ N N/A DAY TANK B LIVELS%TICH 281-1 119 IN USE 746 B Ig DF-4-LS DIESEL GENERATOR FUELOIL DF02,3C2- DIESEL IN USE N N/A DAY TANK B LEVEL SWITCH 281-1 119 IN L4E 310 A 5 DFP-IA AS hlOTOR DRIVFN FUEL OfL DF01,302- DIESEL S OFF Y hfThtC-4 3B TRANSFER PUMP A 281-1 119 ON AND DPDP-6A4 i 311 B 5 DFP-1B AC hlOTOR DRIVEN FUELOIL DF02,302- DIESEL S OFF Y hfThlC-5 4A r TRANSFER PUMP B ,

281-1 119 ON AND DPDP-6B4- 3 5 DFP-IC DC klOTOR DRIVEN FUELOIL 302-281-1 AUA111ARY S OFF N N/A NONE 175 ' -

TRANSFER PUhtP C gg9 OFF Appendix B '17 l

~- . - _ _ _ _ _____ _ __ _ _____

. fm b V U SEQ T CL IDNO EQUIP DESCRIFHON DRAWING BLDGI EVAL SSEL NOTE NORW PWR SUPORT DW INTERCONS R

N EL DEstRED 5 DFP-ID DC DRnTN fUELOIL 302-281-1 AUXILIARY S OFF N N/A NONE 176 TRANSFER PUMP D gg, opy DFT-IA DIESELGENERATORIVELOIL SOUDt BER g IN USE N N/A 421 A 21 302-281-1 STORAGETANK A 105 IN USE DFT-1B DIESEL GENERATOR FUELOIL 302-281-1 SOLTHIBER IN USE N N/A 422 B 21 S STORAGETANK B 105 N USE A 21 DFT-3A DIESELGENERATOR FUELOIL 302-281-1 DIESEL S IN USE N DFP-IA 314 DAY TANK A i19 IN USE 315 B 21 DFT-3B DIESELGENERATOR FUELOIL 302-281-1 DIESEL S IN USE N DFP-IB DAYTANK B 119 IN USE 195 18 Dil-07-LT BORATED WATER STORAGE 302 441-1 BWST S IN USE Y VBDP-8 3 TANK W TL i19 IN USE 194 18 DH-07-LTI BORATT.D WATER STORAGE 302441-1 BWST S IN USE Y VBDP-9 3 TANK LEVEL 119 IN USE 420 1g Dil-37-LT BORATED WATER STORAGE 302 441-1 NAOH TAN S IN USE Y VBDP-4 20 TANK LEVEL 119 IN USE 1 21 DilllE I A DECAY HEAT REMOVAL HEAT 302431-1 AUXILIARY S IDLE N DC EXCHANGER A 075 IDLE 6 21 DlillE-1B DECAY llEAT REhlOVAlliEAT 302431-2 AUXILIARY S IDLE N DC i EXCHANGER B 075 IDLE 4 5 DitP-IA DECAY llEAT PUhtP A 302431-A AUXILIARY g OFF N N/A NOhT

- 075 OFF 5 DIIP-1B DECAY llEAT PUhiP B 302431-2 AUXIUARY S OFF N N/A NONE 5

075 OFF Appendix B 18

.. . . . .~ . . _ - -. . . _ ._

O O O SEQ T CL gDNO EQUIP DESCRIPTION DRA%TNC BLDG / EVAL SSEL NOTE NORM / PWR SUPORT DW INTERCONS R

N EL DE5tRED IN USE N N/A 423 X 21 DHT-1 BORATED WATER STORAGE 302441-1 SOUTH BER S TM 119 IN USE 874 WA WA DHV-095 MALLUPTO PZR AUXIUARY 302 441-1 AUXILIARY N CID6ED N N/A SPRAY ISOtATION VALTT I19 OPEN WA DHV-126 MAKE-UPTO PZR AUXILIARY 302 441-1 AUXILIARY N CIDSED N N/A 873 WA

• SPRAY ISOLATION VAL \T I19 OPEN 298 A 21 DillLIA DIESELGENERATOR 111BE OIL 302-283-1 DIESEL S IDE N DISYSTEM CODI.IR I A 119 IN USE 299 B 21 DtitLIB DIESELGENERATOR LUBE OIL 302-283-1 DIESEL S IDLE .N DJ SYSTEM N IB I19 IN USE 300 A 21 DLHL2A DIESELGENERATOR LUBE OIL 302-283-1 DIESEL S IDLE N DJ SYSTEM COOLER 2A I19 IN USE 301 B 21 DillE-2B DIESEL GENERATOR LUBE OIL 302-283-1 DIESEL S IDLE N DJ SYSTEM M 2B 119 IN USE DPBA-IA 250/125V BATTERY A 206-0!! CONTROL IN USE Y 198 A 15 S DPBC-I A.

108 IN USE IC, A IE DPBA-IB 250/125V BA1TERY B 206 898 CONTROL IN USE Y DFBC-1B, 202 .B 15 S 108 IN USE ID. A IF DPBA-IC 25a'125V BATTERY C 206 051-2 TURBINE IN USE Y DFBC-lO.

434 X 15 S 095 IN USE IH, A II 199 A 16 DPBC-IA BATTERY CilARGER A 206-051-1 CONTROL S IN USE Y KIThlC-21

. 108 IN USE 2BDR I

DPBC-lB BATTERY CilARGER B 206-051-1 CONTROL S IN USE Y h!TMC4 3AL 204 B 16 tot IN USE Appendix B 19

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SEQ T CL ID NO EQUIF DESCRIFDON DRAWING BLDGI EVAL SSEL NOTE NORM / PWR SUPORT DW INTERCONS R

N EL DEstRED 200 A 16 DPBC lC BATTERY CHARGER C 206 051-1 CONTROL S IN USE Y MIMC21 108 IN USE 3BDR 205 B 16 DPBC-ID BATTERY CHARGER D 206051-1 CONTROL S M USE Y MTMC43AR 108 N USE 203 A 16 DFBC-lE BATTERY CHARGER E 20H51-1 CohTROL S STANMY Y MTMC-21 108 STANDBY 4BDR 206 B 16 DPBC IF BATTERY CHARGER F 206451-1 CONTROL S STANDBY Y MTMC43BL 108 STANDBY 435 A* 16 DPBC lO BATTERY CHARGER O 206051-2 TURBINE S IN USE Y MD4C-8 3A 095 IN USE 436 B 16 DPBC-1:1 BATTERY CHARGER H 206451-2 TURBINE S N USE Y MTMC-9 3BL 095 IN L4E 437 AB 16 DPBC-11 BATTERY CHARGER I 206051-2 TURBINE S STANDBY Y DPXS-IC 095 STANDBY 505 A 14 DPDP-IA 250/125V DC MAIN PANEL 3A 206451-1 CONTROL S IN USE Y EPBA-IA 108 IN USE 506 B 14 DPDP-1B 250/125V MAIN FANEL3B 206451-1 CONTROL S N USE Y DFBA-IB 108 N USE X 14 DPDP-IC 250/125V DC MAIN PANEL 3C 206051-1 TURBINE S IN USE Y DFBA-IC 493 095 IN USE 494 X 14 DPDP-3A 250/I25V DC1URBINE 20645I-2 TURBINE S N USE Y DPDP-lC BUllDING PANEL A 095 N USE I

DPDP-3B 250/125V DC TURBNIE 206 051-2 TURBINE IN USE Y DPDP-IC 575 X 14 S l BUIIDING PANEL B I19 IN USE i

t i 577 X 14 DPDP-4B CONTROL COMPLEX DC PANEL 206 4 51-2 CONTROL S N USE Y DPDP-lC 18

! 3B 124 IN USE l Appendix B 20 l

I m - _ - - - _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ - .

. -, g. 11 sEn -T CL IDNO EQUIP DESCRIPTION DRAWING BIAC/ . EVAL SSELNOTE NORM PHR SUPORT DW INTERCONS g EL nessern 206451-1 CONTROL M USE Y DPDP-IA22 '

'578 A 14 DPDP-SA 250/125V DC ES PANEL A S 124 M USE

-579 B 14 DPDP-5B 250/125V DC ES PANEL B 206-051-1 CONTROL 5 N USE Y DPDP-1B 8 124 N USE 553 A 14 DPDP4A 2W125V DC ES DIESEL 206451-1 DIESEL S N L5E Y DPDP-5A 12 OENERATOR PANEL A I19 IN USE B 14 DPDP4B 250/125V DC ES DIESEL 20645l-1 DIESEL 5 N USE Y. DPDP-5B 12 554 GENERA M PANElB 119 IN USE 507 .A 14 DPDP4A 250/125V DC ESSENTIAL 20645I-I CONTROL S N USE Y DPDP-1 A 20 SERVICES PANEL A 108 IN USE 508 B 14 DPDP4B 250/125V DC ESSENTIAL 206451-1 CONTROL S .- N USE Y DPDP-1B 12 SERVICES PANEL B 108 IN USE DPDP-sc 250/125 VOLT DC EFIC PANEL D 206-051 CONTROL S N USE Y- DPDP-IA 580 14 124 N USE 581 14 DPDP-8D 250/125 VOLT DC EHC PANEL D 206451 CONTROL S M USE Y DPDP-1B 124 IN USE 14 DPDS-IA BATTERY 3A DISCONNECT 206 451-1 CONTROL S CIDSED N - N/A 739 SWITCH 108 CLOSED DPDS-1B BATTERY 3B DISCONNEC[ 2064 51-1 CONTROL S CIDSED N N/A 740 14 SHTTCH 108 CIDSED DPDS-IC BATTERY 3C DISCONNECT 206451-2 1URBINE S CLOSED N N/A-736 14 SWITCH 095 CIDSED 582 20 DPTP-5A ENGINEERED SAFEGUARDS DC CONTROL S TEST PANEL 124 Appendix B 21

%) GI w!

SEQ T CL IDNO EQUIP DESCRIPTION DRAWING BLDGf EVAL SSEL NOTE NOILW PWR SUPORT DW INTERCONS R

N EL N 583 20 DFIT-5B ENGINEERED SAFEGUARDS DC CONTROL S TEST PANEL 124 555 20 DFTP4A ENGINEERED SAFEGUARDS DEESEL S DIESELGENERATOR DCTEST gg9 PANEL 556 20

• DFI?4B ENGINEERED SAFEGUARDS DIESEL S DIESEL GENERATOR DC TEST gg, PANEL 509 -20 DFTP-SA ENGINEERED SAFEGUARDS DC CONTROL S TEST PANEL 108 510 20 DFTP-8B ENGINEERED SAFEGUARDS DC COhTROL S 1EST PANTL gog 470 2 DNI MAN XFER S%1TCH FOR 208-041 hfU- AUXIUARY S IN USE Y DPDP-5A 28 POWTR TO MUP-3B AND MUP-5B 31 095 IN USE OR DPDP4B 2s DPXS-IC 206-051-2 TURBINE IN USE Y MTMC4 3B 737 X 14 DPBC-1 INPUT PO%TR S OR MTMC-9 TRANSFER S%TTCH 095 IN USE 3BR 586 20 DRRD42 CRD DC BREAKER CABINTT CONTROL S

- 124 584 20 DRRD-10 CRD AC BREAllR CABINET A- CONTROL S UNTI10 124 585 20 DRRD-1I CRD AC BREAKER CABINET B- CONTROL S UNTIIi 124 587 20 DRRD-2-1 CRD DC BREAKER CABINET CONTROL S UNTTI&2 124 Appendix B 22 m_---____-_______--___-_-_____ .- _ _ _ _ _ - _ _ _ __ _ - -____ ___ ____ - - _ . - -

ry (x U ' () -

SEQ T ct 3DNO EQUIP DESCRIFTION DRAMNG BLDGI EVAL SSELNOTE NORM / PWR SL' PORT DW - INTERCONS R

N EL pam 588 20 DN2-2 CRD DC BREAKER CABINET CONTROL s L%TT 3 & 4 124 589 ~ 20 DRRD-2-3 CRD DC BREAKER CABINET CONTROL s TRIP RESET 124 r

348 A 18 EF-23-FF EFP-1 TO OTSO-B FLOW 302 4 82-1 NTER S IN USE Y g3DP.s 095 IN USE 338 B' 18 EF-24-FF EFP-2 TO 0T30 B FLOW 302-082-1 INTER S IN USE Y VBDP-10 095 IN L5E 349 A 18 EF-25-FT EFP-1 TO OTSO A FLOW 302 4 82-1 INTER S IN USE Y VBDP-8 i 095 N USE 1g EF-26-FT EFP-2 TO OTSO A FLOW 302 482-1 INTER IN USE Y VBDP-10 339 B S 095 IN USE EFW TANK s IN USE Y VBDP-8 330 A 18 EF-98-LT EhtERGENCY FEEDWATER 302 4 82-2 TANK LEVEL i19 IN USE EF-99-LT EitERGENCY FEEDWATER 302 482-2 EFWTANK IN USE Y VBDP-10 33i B 18 s TANK LEVEL i19 IN USE 590 20 EFIC-A EhfERGENCY FEEDWATER CONTROL S N/A N INITIATION ANDCONTROL 124 N/A CABINETA 591 20 EEB EhfERGENCY FEEDWATER CONTROL S N/A N INITIATION AND CONUtOL 124 N/A CABINET B 592 20 EFIC-C EhtERGENCY FEEDWATER CONTROL S N/A N INITIATION ANDCONTROL 124 N/A CABINET C Appendix B 23

hV w[

sEn T CL ID NO EQUIP DESCRIFTION DRAWING BLDG / EVAL SSEL NOTE NORM / PWR Sl? PORT DW INTERCONS R

N EL ymm 593 20 EF1C-D EMERGENCY FEEDWATER CONTROL 3 N/A N DWT10N ANDCONTROL 124 N/A CABINET D 594 20 EFIC-EC-A EMERGENCY FEEDWATER CONTROL S N/A N AUXILLARY EQUIPMENT 124 N/A CABINET A 595 20 EFIC-EC-B EMERGENCY FEEDWATER CONTROL 3 N/A N AUX 113ARY EQUIPMENT 124 N/A CABINET B 5% 20 EFIC-RC-IC EMERGENCY FEEDWATER CONTROL s N/A N AUXILLARY REIAY CABENET IC 124 N/A 597 20 EF1C-RC-ID EMERGENCY FEEDWATER CONTROL 5 N/A N AUXILLARY RELAY CABINET ID 124 N/A 350 A 5 EFP-1 MOTOR DRIVEN EMERGENCY EF01,302- INTER S IDLE Y DPDP.5A 10 FEEDWATER PUMP 082-1 095 IN USE AND WW-2C&2D 340 B 5 EFP-2 TURBINE DRIVEN EMERGENCY 302482-1 INTER s IDLE N EFIC,MS FEEDWATER PUMP 095 IN USE EMERGENCY FEEDWATER 302482-2 EFW TANK IN USE N N/A 332 X 21 EFT-2 S TANK . I19 IN USE 8A EFV41 IlOTWELLISOIATION TO 302482-1 INTER s CWSED Y DPDP4B1&

343 TURBINE DRIVEN EFP-2 EF-06 095 OPEN 2 8A EFV-02 IlOTWELLISOIATION TO 302-082-1, INTER S C WSED Y DPDP-8A I A 344 MOTOR DRIVEN EFP-l EF47 095 OPEN 2 1

8A EFV-03 CDT-1 ANDElT-2ISOIATION 302 4 82-I. INTER S CLOSED N NO POWER 345 TO EFP-1 EF-02 095 OPEN AVA11ABLE Appendix B 24

7. 7s

\ ( '

SPA) T CL ID No EQUIF DESCRIPTION DRAWING BLDG / EVAL . SSELNOTE NORM / FWR SUPORT DW INTERCONS

" marssesn g EL CIDSED N ~NOPOWER 346 8A EFV44 CDT-l ANDSfT-2 ISOLATION 302 4 82-1 INTER S TO EFP-2 EF03 095 OPEN. AVAILABII i

868 N/A EFV-36 HOTWELLSHUTOFFTO EFP-1 302-082-1 TURBINE N CIASED 'N N/A AND EFP-2 096 OPEN EE17,302- INTER OPEN , Y .- DPDP-58 29 337 B 8B

• EFV-55 EFP-2 TO OTSO B CONTROL VALVE 082-1 S

AND VBDP-095 CONTR%

10 336 B 8B EFV-56 EFF-2 TO OTSO ACONTROL EFIt,302- INTER S OPEN Y . SPSP-5B 29 VALVE 082-1 095 CONULOL AND VBDP-10 EFV-57 EF7-1 TO OTSO B CONTROL EF19,302- INFER OPEN Y DPDP-SA 29 347 A 8B S VALVE 082-1 095 ACONTRO AND VBDP-8 L

EFV-58 EF20,302- INTER OPEN Y DPDP-5A 29 353 A 8B EFP-1 TO OTSO A CONTROL S VALVE 082-1 119 COfGROI. AND VBDP-8 20 EGCP-IA EhiERGENCY DIESEL DIESEL S N/A N 557 GENERATOR ACONTROL I19 N/A PANEL 20 EGCP-1B EMERGENCY DIESEL DIESEL S N/A N 558 GENERATOR BCONTROL I19 N/A PANEL ,

20 EGCP-2A EktERGENCY DIESELGEN A DIESEL S N/A N 559 ELENCAI.WMENT I19 N/A CABINET 20 EGCP-2B EktERGENCY DIESELGEN B DIESEL S N/A N 562 ELECTRICAL EQUIPh1ENT I19 N/A CABINET Appendix B 25

O O O Sao T CL D NO EQUIP DESCRIPTION DRAWING BLDG / EVAL $$EL NOTE NORM / PWR SUPORTDW INTERCONS R

N EL DEstRED 563 20 EGCP-3A DEESELGENERATOR A DIESEL S COMOL FOWER RELAY g39 CABINET 564 20 EGCP-3B DIESELGENERATOR B DIESEL S COWROL POWER REIAY g39 CABINET 565 20 EGCP-4A DIEscLGENERATOR APO%IR DIESEL S e CIRCLTT BREAKER PANEL g39 566 20 EGCP-4B DIESELGENERATOR B POWER DEESEL S CIRCUIT BREAKER PANEL gg9 EGDG-IA DIESELGENERATOR A EG05 MTl3, DIESEL STANDBY Y DPDP-5A, 312 A 17 S DPDP4A, 302-282-1 119 IN USE EDG START AIR EGDG-1B DIESELGENERATOR B EG06,lLITl4, DIESEL S STANDBY Y prDr.

313 B 17 SB,DPDP4B, 302-282-1 119 IN USE EDG STARTING AIR EGT-lA EDG A AIR RECEIVER I A 302-282-1 DIESEL IN USE N N/A-317 A 21 S 119 IN USE EGT-lB EDO A AIR RECEIVER IB 302-282-1 DIESEL S .N USE N N/A 318 A 21 i19 IN USE EGT-2A EDO B AIR RECEIVER 2A 302-282-1 DIESEL S IN USE N N/A 319 B 21 I19 IN USE EGT-2B EDG B AIR RECEIVER 2B 302-282-1 DIESEL S IN USE N N/A 316 B 21 i19 IN USE 8B EGV-36 EDO A AIR START SOLENOID EGOS,302- DIESEL S Y DPDP4A 12 294 A '-

VALVE 282-I 119 Appendix B 26 m- _ - - - - - - - - - - - - -- - - - - - - - - . - . - - - - - - - _ - - - - - - - -------__ __. _ _ _ _ . - - _

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SEQ T CL ID NO EQUIP DESCRIFEION DRAWING BREG/ EVAL SSELNOTE NORM / FWR SUFORT DW INTERCONS EL DESIRED EGV-37 EDO A AIR STARTSOLEbotD DIESEL S Y DPDr4A12 295 A 8B EG0S. 302-VALVE 252-1 g39 8B EGV-40 EDO B AIR STARTSOLENOID EG06,302- DEESEL S Y DPDP4812 296 B VALVE 282-1 g39 EDG B AIR STARTSOIINOID EG06 DIESEL S Y DPDP4812 297 B 8B

• EG V-41 VALVE gg9 EGV-52 EDO A AIR START 3-WAY 302-2s2-1 DEESEL N EGV,36 747 A 7 VALVE g39 EDG A AIR START 3-WAY 302-282-1 DIESEL N EGV-37 748 A 7 EGV-53 VALVE g39 749 B 7 EGV-54 EDG B AIR START 3-WAY 302-282-1 DIESEL N EG V-40 VALVE g39 750 B 7 EGV-55 EDG B AIR START 3-WAY 302-252-1 DIESEL N EGV-41 VALVE g39 751 A 8B EGV-56 EDG A AIR START VALVE 302-282-1 DIESEL N EGV-52 119 A 8B EGV-57 . EDG A AIR START VALVE 302-282-1 DIESEL N EGV-53 752 119 753 B 8B EGV-58 EDG B AIR START VALVE 302-282-1 DIESEL N EGV-54 119 754 B 8B EGV-59 EDG B AIR START VALVE 302-282-1 DIESEL N EGV-55 119 20 ERI EVENTS RECORDER CABINET I CONTROL s N/A N 652 I45 N/A 20 ER2 EVENTS RECORDER CABINET 2 CONTROL S N/A N 653 145 N/A Appendix B 27

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s j.3 kJ O SEQ T .CL ID NO EQUIFDESCRIFTION - DRAWING BLDG / EVAL $5ELNOTE . NORM / FWIt SUyORT DW INTEDCONS

" .nsaamen EL ER3 EVENTS RECORDER CABINET 3 CDN11tOL S N/A N 654 20 145 N/A ER4 EVENTS RECORDER CABINET 4 CONTROL S N/A N 655 20 145 N/A ERS EVENTS RECORDER CABINET 5 CONTROL S N/A N 656 20 145 N/A ER6 EVENTS RECORDER CABINET 6 CONTROL S N/A N 657 20 145 N/A ER7 EVENTS RECORDER CABINET 7 CONTROL S N/A N-658 20 145 N/A EVENTS RECORDER CABINET S CONTROL S N/A N 659 20 ERS 145 N/A ES SYSTEM CHANNELTEST CONTROL S N/A N 660 20 ESCC-1 NU I 145 N/A ESCC-IA ES SYSTEM CHANNEL CABINET ' CONTROL S N/A N 661 20 IA 145 N/A 662 20 ESCC-1B ES SYSTEM CHANNELCABINET CONTROL S IB 145 ESCC-2 CONTROL S N/A N 663 20 ES SYSTEM CHANNELTEST CABINET 2 145 N/A ESCC-2A ES SYSmlCHANNELCABINET CONTROL S N/A N 664 20

• 2A 145 N/A 665 20 ESCC-2B ES SYSTEM CHANNELCABINE1 CONTROL- S 2B 145 ESCC-3 ES SYSTEM CllANNELTEST CONTROL S N/A N 666 20 ' ~

CABINET 3 I45 N/A Appendix B 28

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SEQ T CL ID NO EQUIF DESCRIPTION DRAwTNG BLDG / EVAL SSEL NOTE NORM / PHR SUPORT DW INTF N R

EL DESIRED N

ESCC-3A ES SYSTEM CHANNELCABINET CONTROL S 'WA' N 667 20 3A 145 N/A t 677 20 N3B ES SYSTEM CHANNELCABNET CONTROL S 38 g43 ESCP-1 MECHANICALINTERIDCK CON 11tOL S N/A .N 668 20

• CONTROL M 145 N/A ESCP-4A ENGINEERED SAFEOUARDS M OL S N/A N 669 20 ACTUATION RELAY CABNET 145 N/A 4A ESCP-48 ENGNEERED SAFEGUARDS CONTROL S N/A N 670 20

- ACTUATION RELAY CABINET 145 N/A 4B ESCP-4C ENGNEERED SAFEGUARDS CONTROL S N/A N 671 20 ACTUATION RELAY CABINET 145 N/A 4C ESCP-4D ENGINEERED SAFEGUARDS CONTROL S N/A N 672 20 ACIVATION REIAY CABINET 145 N/A 4D 20 ESCP-SA ENGNEERED SAFEGUARDS CONTROL S N/A N 673 ACTUATION REIAY CABINET 145 N/A SA 20 ESCP-3B ENGINEERED SAFEGUARDS CONTROL S N/A N 674 ACTUATION REIAY CABINET I45 N/A SB ESCP-5C ENGINEERED SAFEGUARDS CONTROL S N/A N 675 20 ACTUATION REIAY CABINET 145 N/A SC Appendix B 29

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_( t 4 G s.s' (Ol-seq T CL D NO EQUIP DESCRIPTION DRAWIN;; BLDGf EVAL SSEL NOTE NORM / PWR SUPORT DW INTERCONS R

N EL ymmm 676 20 ESCP-5D. ' ENGINEERED SAFEGUARDS CONTROL 5 N/A N ACTUATION REIAY CABWET 145 N/A SD 483 20 ESP 8C-3Al ENGNEERED SAFEGUARDS WIER S WA N PRESSURE 5%TFCH CABINET 093 N/A 3Al 484 20 ESP 9C-3A2 ENGINEERED SAFEGUARDS INTER S N/A N PRESSURE SWITCH CABINTT 095 N/A 3A2 485 20 ES N 3A3 ENGNEERED SAFEGUARDS MTER S N/A N PRESSURE 5%1TCH CABINET 095 N/A 3A3 471 20 ESN3A4 ENGWEERED SAFEGUARDS AUXIIJARY S N/A N PRESSURE SWITCH CABINET 095 N/A 3A4 486 20 ESPSC-3B1 ENGINEERED SAFEGUARDS INTER S N/A N PRESSURE SWITCH CABINET 095 N/A 3BI 487 20 ES N 3B2 ENGINEERED SAFEGUARDS INTER S N/A N PRESSURE SWITCH CABINET 095 N/A 3B2 488 20 ES N 3B3 ENGINEERED SAFEGUARDS INTER S N/A N PRESSURE SWITCH CABINET 095 N/A 3B3 678 20 FSCP-1 CONTROL PANEL WITH CONTROL S N/A - N BATTERY RACK AND A10DUIIS 145 N/A 20 FSCP-2 LEASED LINE ANNUNCIATOR AUXILIARY S N 'A N 472 095 N/A Appendix B 30

<a-.------_--------_-------___--__ - _ _ - - - - - - - . _ - _____ _ _ _ . _ __

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.%/ v SEQ T CL gDNO EQUIP DESCRIFFION pgAw1Nc BLDGi EVAL SSEL NOTE NOBLW P%R SUPORT DW INTERCONS R

N EL DESIRED 20 F3CP-3 LEASED IJE ANhMTOR CONTROL s N/A N 679 145 N/A 5 NP-7 AUXIIJARYIT.EDWATER PUMP 3024814 TUltBINE s OFF N N/A 446 7 093 OFF 8A FWV-14 FEEDWATER PUMP A SUCTION FW22,302 1URBINE s OPEN Y MTMC-512A 463 B

. ISOIATION VALVE 081-2 121 CIDSED 464 A 8A FWV-15 FEEDWA1TR PUMP B SUCTION FW23,302- TURBINE s OPEN Y MTMCJ 148 ISOLATION VALVE 081-2 121 CWSED 460 B 8A FWV-28 FEEDWATER PUMPS FWl9,302- TURBINE S CWSED Y MTMC-5 IIC DISCHARGE CROSSTIE 081-2 109 CLDSED ISOIATION VALVE 419 B 8A NV-29 OTSO B MAIN BWCK VALVE FWI4. 302- INTER S OPEN Y MTMC-512C 081-1 142 C WSED 417 A 8A NV-30 OTSO A MAIN BWCK VALVE FWI3,302 INTER S OPEN Y MWC-314C 081-1 IM C WSED 418 A 8A FWV-31 OTSO AIDW IDAD BIDCK FWil 302- INTER S OPEN Y MTMC-3 I4A VALVE 088-1 IM CIDSED 414 B 8A NV-32 OTSO B IDW IDAD BIDCK FW 12,302 INTER s OPEN Y M111C-512B VALVE -

081-1 IM CIDSED 415 B 8A N V-33 OTs0 B STARTUP BIDCK FW31,302- INTER S OPEN Y DPDP-8B 10 VALVE 081-1 IM CIDSED 416 A 8A FWV-36 OTSO A STAR 1UP BIDCK FW30,302- INTER S OPEN Y DPDP-8A 8 VALVE 081-1 IM C WSED 448 5 GWP-IA CONDENSATE INJECTION 302-142-1 1URBINE s ON N N/A PUMP 3A 095 '- OFF Appendix B 31

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SEQ T CL ID No EQUIP DESCRIFTION DRAWING BLDG / EVAL : SSELNOTE NORM / -PWR SUPORT DW INTERCONS EL asurern h

l 5 GWP-IB CONDENSATE INJECTION 302-142-I 1URBINE S ON N N/A 449 FUMP3B 095 OFF 7 GWY1% GWP-I A CONTROL VALVE 302-142-1' TURBINE S CONTROL N WA 450 095 OFF 20 HTCP-2 N EMERGENCY LOAD ALDG11ARY S . N'A N 473

. SHEDDING-HEATTRACM 095 N/A 20 HTCP-3 ~ EDG-B EMERGENCY IDAD AUXILLARY S N/A N 544 SHEDmNG HEATTRACM i19 N/A HTCP4 EDG4 EMERGENCY LOAD AUXILIARY S N/A N 474 20 SHEDDING-HEATTRACLNG 093 N/A 20 HTCP-5 EDG A EMERGENCY LOAD AUXILLARY S N/A N 545 SHEDDING-HEATTRACN I19 N/A HVAC-16A IIVAC CONTROLCABINET 16A AUXILLARY 3 N/A N 475 20 093 N/A 20 HVAC-16B HVAC CONTROLCABINET 16B AUXILLARY S N/A N 476 095 N/A 20 HVAC-17A HVAC CONTROL CABINET 17A AUXILLARY S N/A N 546 119 N/A 20 HVAC-17B HVAC CONTROLCABINET 17B AINIllARY $ N/A N 547 119 N/A 20 HVAC-19 HVAC CONTROLCABINET 19 DIESEL S N/A N 567 119 N/A 20 tiVAc-20 HVAC CONTROLCABINET20 DIESEL S N/A N 568 I19 N/A 9

INSTRUMENT AIR IIEADER TURBINE IN USE Y TPC 428 I8 1A M PT 302 271-1 S

PRESSURE 095 IN USE Appendix B 32 1 - - - - - - . _ - - - - - - - - - - - - - - _ - - - - - _ - - - - - - _ - - - - - _ - _ -_ - _--_ ._. . __

g-_ - .

\ b V-SEQ T CL ID NO EQUIP DESCRIFTION DRAWING BLDGf EVAL SSEL NOTE NOIL'4f PWIt SUPoitT DW INTERCXmS R DESIRED N

EL wl2-PS mSTRUMENT AIR WI. N2,_ M tBNE IMI N N/A 738 X 13 S COMPRESSORIDAD'UNIDAD 302-271-1 095 CONUtOI, PRESS SWITCH IADit-l INSTRUMEM AIR DRYER I IA03,302- TLTBINE Y N12 429 A* 21 S 3AE 271-1 095 IN USE INSTRUMENT AIR AFTER- 302-271-1 TURBINE S N SC SYSTEM 430 A 21

• IAHE 1A COOLER A 095 IN USE IAHE-1B INSTRUMENT AIR AFTER- 302-271-1 TURBIhI S N SC SYSTEM 431 B 21 COOER B 095 IN USE

]2 IAP-IA INSTRUMENT AIR IA01,302- TUltBINE IDLE Y MTSW E 426 A S 2C,DPDP-3A COMPRESSOR A 271-1 095 IN USE i1. AND SC SYSTEM IAP-lB INSTRUMENTAIR 1A02,302- TURBINE S IDE Y - MTSW-3D 427 B 12 2C, DPDP-3B COMPRESSOR B 271-1 095 IN USE

11. AND SC SYSTEM IAT-IA INSTRUMENT AIR RECEIVER A 302-271-1 TURBLNT IN USE N N/A 432 A 21 S ,

095 - IN USE IAT-lB INSTRUMENT AIR RECEIVER B 302-271-1 TURBINE S IN USE N N/A 433 B 21 095 IN USE AIR SUPPLY TIE IATO SA 302-271-2 TURBLNE N OPEN N N/A 856 N/A 1AV-010 095 CIDSED N/A IAV431 AIR SUPPLY BYPASS FOR IADR- 302-271-1 TURBINE N CIDSED N N/A '

857 I 095 OPEN 1ADT-2 ISOLATION 302-271-1 TURBINE N OPEN N N/A 858 N/A N/A IAV-036 095 CIDSED Appendix B 33

f'r r~- ,~

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-SEQ T CL ID NO EQUIP DESCRIPTION DRA%1NG. BLDG / EVAL - SSELNOTE NORM / F%R SUPORT DW INTERCONS R

N EL DESIRED IAITT-1 ISOIADON 302-271-1 TLRBINE N OPEN N . N/A -

859 N/A N/A 1AV437 095 C wSED N/A IAV-048 lADT-9 ISOLATION 302-271-1 RRBINE N OPEN N N/A 862 N/A 095 CLOSED RRIENE OPEN N N/A .

863 N/A N/A IAV-06 IADT-10 ISOLATION 302-271-1 N 095 C wSED 864 N/A N/A IAV450 IADT-3 ISOLATION 302-271-1 IURBINE N OPEN N .N/A 095 CwsED 865 N/A N/A IAv-051 lADT-71SOIATION 302-271-1 RRBibT N OPEN N N/A 095 CLOSED IADT-3 ISOLATION 302-271-1 TURBINE N OPEN N N/A 866 N/A N/A IAV48 i 095 CLOSED OPEN N- N/A 867 N/A N/A IAV49 IADT-7 ISOLATION 302-271-1 TURBWE N 095 CwSED IAV-188 IAP-I A WADER / UNLOADER 1A01,302 TURBINE S- OFF Y DPDP-3A II 424 A 8B VALVE 271-1 , 095 N USE 8B IAV-189 IAP-IB wADEPAJNIDADER IA02,302- TURBINE S OFT Y DPDP-3B II -

425 B VALVE 271-1 095 IN USE N/A N/A IAV-388 1ADT-8 ISOIADON 302-271-1 TURBINE N OPEN N N/A 860 '

095 C wSED N/A 1AV-393 IADT-7 ISOLATION 302-271-1 TURBIhT N OPEN N N/A 861 N/A 095 CwSED ICS MAIN CONTROL BOARD CONTROL S N/A N 680 20 145 N/A 681 20 ICS-1 INTEGRATED CONTROL CONTROL S SYSTEM CABINET I 145 Appendix B 34

+ . _

l?

[

seq T CL ID NO EQUIP DESCRIPTION DRAWING BLDGf EVAL SSELNOTE NORMI FWR SUPORTDW INTEREONS

= . . . . ,

EI.

l 682 20 BCS-2 INTEGRATED CONTROL CONTROL s i SYSTEM CABINET 2 145 683 20 ICS 3 NTEGRATED CONTIOL CONTROL s SYS1TM CABNET3 145 684 INTEGRATED CONTROL CONTROL S 20

• BCs-4 SYSTEM CABINET 4 145 685 20 BCS-S NTEGRATED CONIROL CONTROL 3 SYSTEM CABINET S 145 MAIN STEAM UNE A-2 INTER IN USE Y. VBDP-s -

365 A is MS-106-PT 302 4 11-1 S PRESSURETRANSMITTER I19 ' IN USE MS-107-PT MAIN STEAM LINE A-1 302-011-1 NTER N USE Y. VBDP-10 378 B 13 S PRESSURETRANSMITTER I19 IN USE 364 A 1g MS-10s-PT MAIN STEAM LINE A-2 302-011-1 INTER S IN USE Y \1BDP-9 PRESSURETRANSMITTER I19 IN USE 18 MS-109-FT MAN STEAM UNE A-l 302-01I-1 INTER S IN USE Y VHDP-Il 379 B PRESSURE TRANSMITIT.R I19 IN USE 388 A la MS-l10-PT MAIN STEAM LINE B-2 302-011-1 INTER g IN USE Y vigDP-s PRESSURE TRANSMITTER. I19 N USE la MS-11I-rr MAIN STEAM UNE B-1 302-011-1 INTER S IN USE Y. VBDP-10 394 B PRESSURETRANSMITTER I19 IN USE MS-Il2-PT MAIN STEAM UNE B-2 302-011-1 INTER IN USE Y \1tDP-9 389 A 18 S PRESSURE TRANSMITTER I19 IN USE 395 B Ig MS-n3-rr MAIN STEAM ilNE B 1 302-011-1 INTER S IN USE Y VBDP-Il PRESSURE TRANSMITTER I19 _ IN USE Appendix B 35 i _ .. _

fm- ry [

0' SEQ. T CL ID NO EQUIP DESCRIPTION DRAWING SLDC/ EVAL SSEL NOTE NORW PWIL St' PORT DW INTERCOM 5 R

N EL DESIRED A 7 MsV-025 Anf0 SPHERIC DUMP VALVE A 3024111 INTER S CIDSED Y VilDP-8,IA, 372 EFIC t19 CONTROL MSV426 ATMOSPHERIC DUMP VALVE B 302 4 11-1 INTER 3 CLOSED Y VHDP-10,IA, 3% B 7 E

t19 CONTROL MAIN STEAM UNE A-2 SAFETY 302-011-1 INTER s CIDSED N N/A 373 A 7

• MSV-033 VALVE I19 IN USE MSV434 MAIN STEAM UNE A-I SAFETY 302411-1 INTER CLOSED N' N/A 380 A 7 S VALVE I19 IN USE 7 MSV435 MAIN STEAM UNE B-1 SAFETY 302 011-1 INTER S CLOSED N N/A 384 B VALVE I19 IN USE 7 MSV-036 MAIN STEAM UNE B-2 SAFETY 302-011-1 INTER S CIDSED N N/A 397 B VALVE I19 IN USE MSV-037 MAIN STEAM LINE A-2 SAFE 1Y 302411-1 IN1ER CIDSED N N/A 374 A 7 S VALVE I19 IN USE MSV-03: hlAIN STEAM UNE A-1 SAFETY 302-011-1 INTER CLOSED N N/A 381 A 7 S VALVE I19 IN USE 7 MSV-039 MAIN STEAM UNE B-1 SAFETY 302-011-1 INTER CLOSED N N/A 385 B S VALVE .

I19 IN USE 382 A 7 MSV-040 MAIN STEAM UNE A-1 SAFETY 302411-1 LVFER S CIDSED N N/A VALVE I19 IN USE B 7 htSV441 MAIN STEAh! UNE B-2 SAFETY 302-01: i INTER S CLOSED N N'A 398 VALVE I19 IN USE MSV442 MAIN STEAM UNE A-2 SAFETY 302411-1 INTER CIDSED N N/A 375 A 7 S YAI U l19 .. IN USE Appendix B 36

,y. - , ,

y SEQ T CL ID NO EQUIP DESCRIPTION ' DRAWING BLDGf EVAL SSEL NOTE NORM / FWR ' SUPORT DW INTERCONS

'R N EL Dem

.383 A 7 MSV443 MAIN STEAM 1JNE A-1 SAFETY 3024Il-1 INTER S CLOSED N N/A VALVE I19 IN USE B 7 MSV444 MAIN STEAM LINE B-I SAFETY 302 4 11-1 INTER S C1DSED N N/A 386 VALVE I19 IN USE 400 B 7 MSV443 MAIN STEAM LNE B-2 SAFETY 302 4 11-1 INTER S CIDSED N N/A VALVE I19 IN USE 376 A 7 MSV 046 MAIN STEAM UNE A-2 SAFETY 302 4 11-1 INTER' S CLOSED N N/A VALVE I19 IN USE 387 B 7 MSV447 MAIN STEAM IJNE B-1 SAFETY 3024Il-l INTER S CLOSED N N/A VALVE 119 IN USE 401 B 7 MSV-04: MAIN STEAM UNE B-2 SAFETY 3024H-1 INTER S CIDSED N N/A VALVE I19 IN USE 377 B 8A MSV-055 OTSO ATO EFTB-1 STOP CHECK MSto,302- INTER S OPEN Y DPDP-8B 14 011-1 119 OPEN 402 B 8A MSV-056 OTSO B TO EFTB-1 STOP CHECK MSO9,302- INTER S OPEN Y DPDP-8B 16 011-1 119 OPEN 876 N/A N/A MSV-297 MSDT-22 ISOLATION VALVE 302 4 11-1 INTER N OPEN N N/A

• 119 C1DSED 877 N/A N/A MSV-299 MSDT-23 ISOIATION VALVE 3024Il-1 IN11R N OPEN N N/A 119 CLOSED 878 N/A N/A MSV-301 MSDT-241SO1ATION VALVE 302-011-1 INTER N OPEN N N/A 119 CIDSED 879 N/A N/A MSV-303 302411-1 INTER N OPEN N N/A MSDT-251SOLATI,0N VALVE 119 CLOSED Appendix B 37 a_____-_____-__-________. . - ..

s -g gs

' SEQ T CL ID NO EQUIP DESCRIPTION DRAWING BLDG / EVAL SSEL NOTE . NORM / FWIt SUPORTDW INTERCONS R

EL DESIRED N

MAIN STEAM LINE A 2 MS18,302 INTER OPEF4 - Y DPDP4A11 354 X 7 MSV-411 - S ISOLATION VALVE 011-1 119 CLOSED MSV-4tl- MSV-411 AIR RESERVOIR I 308-335 INTER N USE N N/A 366 X 21 S ARI 119 M USE MSV-411 AIR RESERVOIR 2 308-335 INTER IN USE N N/A 367 X 21 MSV-411- S

• AR2 119 IN L5E MSV-4II- MSV-4II AIR RESERW)lR3 305-335 INTER IN USE N N/A 368 X 21 S AE3 119 IN USE 356 X 8B MSv-4 t i. MSV-411 CONTROL MSl8,308- INTER S Y DPDP4All SVI 335 339 MSV-4 H- MSIS 308 INTER Y DPDP-8A 11 357 X 8B MSV-411 CONTROL S t SV2 335 gg9 358 X 8B MSV 411 MSV-4 tl CONTROL MSIS 308- INTER S Y DPDP4A 11 SV4 335 gg9 j X 8B MSV- MSV-41I & MSV-412 CONTROL MS18,308- INTER S Y DPDP-8A 11 359 411/412-SV5 335 g39 360 X 8B MSV- MSV-4tl & MSV-412 cOrrrROL MS18. 308 INTER S Y DPDP4A H 411/412-SV6 , 335 gg9 355 X 7 MSV-412 MAIN STEAM LINE A-1 MS18,302 INTER S OPEN Y DPDP4AII ISOLATION VALVE 011-1 H9 M ED INTER IN USE N N/A 369 X 21 MSV-412- MSV-412 AIR RESERVOIR I 308-335 S ARI 119 IN USE MSV-412- MSV-412 AIR RESERVOIR 2 308-335 IN'IER IN USE .N. N/A 370 X 21 S AR2 119 IN USE Appendix B 38 u

l' sEn T CL ID NO EQUIP DESCRIFTION DRA%1NC BLDG / EVAL SSEL NOTE NORMt -PWR stTORT DW INTERCOl45 g EL rwaara kSV-412 MSV 412 AIR RESERVOIR 3 308-335 INTER M USE :N N/A 371 X 21 S AR3 I19 - N USE -

361 X 8B MSV-412 MSV 413 CONTROL MSl8,305- DTTER S _Y- DPDP4A 11.

SVI 335 gg9 MSV-412 CONTROL MSl8,308- INTER Y DPDP4A 11 -

362 X SB MSV-412- S

'SV2 335 gg, 363 X 8B MSV-412- MSV-412 CONTROL MS18,308- DmER S Y DPDP4A11 SV4 335 g39 399 X 7- MSV-413 MAIN STEAM IJNE B-1 MSl9,302- INTER S Y DPDP4A 11 ISOLA 110N VALVE 011-1 gg9 MSV-413 AIR RESERVOIR I 308-335 INTER IN USE Y MtA L 403 X 21 MSV-413- S ARI 119 IN USE I

MSV-413- MSV-413 AIR RESERVOIR 2 308-335 INTER IN USE N ' N/A 404 X 21 S AR2 119 IN USE  ;

t MSV-413 AIR RESERVOIR 3 308-335 INTER IN USE N N/A 405 X 21 MSV-413- S t AR3 119 IN USE I

406 X 8B MSV-413 MSV-413 CONTROL MS19. 308- INTER S Y DPDP-SA 11 '

SVI , 335 g39 ,

407 X 8B MSV-413- MSV-413 CONTROL MS19,308- INTER S Y DPDP-8A ll  !

SV2 335 g39  !

408 X 8B MSV-413 MSV-413 CONTROL MS19,308- INTER S Y DPDP-SA 11

, SV4 335 gg9 l

MSV- MSV-413 & MSV-414 CONTROL INTER Y DPDP-SA ll 409 X 8B MS19. 308- S 413/414-SV5 335 gg9 Appendix B 39 i

D --- - -_--- -__- -- .n..s. ., .

(G/ l 4 SEQ T CL ID NO EQL1F DESCRIFTION DRA%TNG BLDGI EVAL SSELNOTE NORM / F%R SLTORT DW INTERCONS

.R-N EL DESIRED 410 X 8B MSV- MSV-413 & MSV-414 CONTROL MS19,308 INTER S Y DPDP4A Il 413/414 SV6 335 g39 L

390 X '7 MSV-414 MAIN STEAM UNE B-2 MS-19,302- INTER g OPEN Y' DPDP4AII ISOLATION VALVE 011-1 119 CtOSED INTER IN USE N N/A 391- X 21 MSv-414 MSV-414 AIR RESERVOIR I 308-335 3

~# 119 IN USE INTER IN USE N N/A 392 X 21 MSV-414- MSV-414 AIR RESERVOIR 2 308-335 S E 119 IN USE 393 X 21 MSV414- MSV-414 AIR RESERVOIR 3 308-335 INTER S IN USE N N/A AR3 119 IN USE 411 X 8B MSV-414- MSV-414 CONTROL MS19. 308- INTER S Y DPDP-SA ll SV1 335 gg9 412 X 8B MSV-414- MSV-4I4 CONTROL MSl9,308- INTER S Y DPDP-SA i1 SV2 335 g39 413 X 8B MSV-414- MSV-414 CONTROL MSl9,308- INTER S Y DPDP-5A II SV4 355 g39 511 20 MTCP-IA UNDERVOLTAGE TEST CONTROL S N/A N CABINET A - 108 N/A 512 20 MTCP-IB UNDERVOLTAGE TEST CONTROL S N/A CABINET B 108 N/A 479 A 1 MTMC-03 480V ES MCC3Al 206417 AUXILIARY S IN L5E Y MTSW-3F 3D 095 IN USE AND DPDP- ,

SA9 Appendix B 40

y-(x b O SEQ T CL ID NO EQUIP DESCRIPTION DRAMING BLDC/ EVAL SSEL NOTE NORM / PWR SUPORT DW INTERCOM 5 R L N EL N 549 A I nrruc44 4 0V ES MCC 3A2 206417 AUXILIARY S IN USE Y MT3W-3F 2B I19 IN USE AND N SA9 550 P 1 MTMC45 480V ES MCC 3BI 206417 AUXILLARY S IN USE Y MTSW-30 119 N USE 28AND DPDP-SB 9 480 B 1 Mnaco6 4s0V ES MCC 3B2 206 4 17 AUXILIARY S IN USE Y MTSW-30 095 IN USE 3D AND DPDP-3B 9 551 AB 1 wrMC47 4s0V ES MCC 3AB 206-017 AUXILIARY S IN USE Y MTXS-I 119 IN USE 569 A 1 kmIC4: 480V PRESSURIZER HEATER 206416 INTER S IN USE Y MTSW-3C MCC3A 319 IN USE IC AND DPDP-3A 11 570 B 1 MTMC49 4:0V PRESSURIZERIIEATER 206-016 INTER S IN USE Y MTSW-3D MCC3B I19 IN USE IC AND DPDP-3B il 576 A 1 MnIC 12 4:0V TURBINE MCC 3A 206-016 TURBINE S IN USE Y MTSW-3J 3C I19 IN USE AND DPDP-3A 13 477 1 MnIC-1 4s0V REACTOR MCC-3 A2 206-016 AUXILLARY S IN USE Y MTSW-3C 095 IN USE 548 A I MTMC-21 480V ES MCC 3A3 206-017 AUXILLARY S IN USE Y MTSW-3F 2C I19 ' IN USE AND DPDP.

5A9 478 B 1 M u tC-22 480V ES MCC 3B3 206-017 AUXILIARY S IN USE Y krI5W-30 095 IN USE 2C AND DPDP-5B 9 Appendix B 41

n p - p Y '

SEQ T CL IDNO EQUIP DESCRIFTION DRAHTNG BLDG / EVAL SSEL NOTE NOftW FWR SUPORT DW INTERCONS R

N EL DESIRED 513 A 3 MTSW-2C 4160V ES 3A(NOltTH) 206411 CONTROL $ N USE Y MTSW-2D 108 IN USE 514 A 3 MTSW-2D 4160V ES 3A(SOLTTH) 206411 CONTROL S N USE Y EODG-IA 108 EIUSE AND DPDP-SA10 515 B 3 . MTSW-2E 4160V ES 3B(NORTH) 20H11 CONTROL S IN USE ~ Y MTSW-2F los IN USE 516 B 3 wrSW-2F 4164Tf ES 3B(SOUTH) 206411 CONTROL S N USE Y- EGDO1B los IN USE AND DPDP-5B 10 495 A* 2 MTSW-3A 480VTURBME AUXIUARY BUS 206411 TURBINE S N USE Y M13W-3J IC A 095 IN USE AND DPDP-3AI3 496 A 2 MTSW-3C 480V REACTOR AUXILIARY 206411 ' TURBINE S IN USE Y MTSW-3F 3A BUS A 095 IN USE AND DPDP-3A ll 497 B 2 MTSW-3D 4s0V REACTOR AUXILIARY 206411 TURBINE S IN USE Y MTSW-3J IC BUS B 095 IN USE AND DPDP-3B il 6()2 A 2 MTSW-3F 480V ES BUS 3A 20H17 CONTROL S IN USE Y MISW-2D 124 IN USE II. DPDP-5A

9. AND DPDP-5A 10 603 A 4 MTSW-3F-T 4160/480V ES BUS 3A 206 4 17 CONiltOL S IN USE N N/A TRANSFORMER 124 IN USE 604 B 2 krrSW-30 480V ES BUS 3B 206-017 CONTROL S IN USE Y MTSW-2F 4, 124 IN USE DPDP-5B ,

s AND DPDP-SB 10 Appendix B 42

f-s g m

/

seq T CL ID No EQUIP DESCRIPTION DRAWING BIEGI EVAL SSEL NOTE NORM / PWR SUPORT DW INTEDCONS R

y EL DESIRED 4 MTSW-30-T 4:60/4:0V ES BUS 3B 206 417 CONTROL IN USE N N/A 605 B S TRANSFORMER 124 N USE 498 B 2 MTSW-3J 4s0V PLANT AUXIUARY BUS 2064II TURBINE S N USE Y MTSW-2E 095 IN USE 12.DPDP-3B 10 AND DPDP-3B 10 499 B 4 MTsW-3J-T 416w4 0VP1ANTAUXIUARY 206411 TURBINE S N USE N N/A BUS MSN 095 N USE

^

606 X 2 MTXS-1 ES MCC 3ABINPUT POWER 206 017 CONTROL S IN USE Y MTSW-3F TRANSFER 5%TTCH 124 IN USE AND DPDP-5A.OR MTSW-30 AND DPDP-SB 41 1g MU 002-FT PRESSURE TO RCP SEALS 302 4 61-3 AUXIMARY S IN USE Y NNI-X OR 095 IN USE NY 742 7 MU403 MUV-5I CONrTROL 308-827 AUXIUARY S IN USE Y IA POC I19 IN USE 8B MU403-SV MUV-51 AIR FAILIDCK MU54,308- AUXIUARY S . STANDBY Y VBDP4 23 172 827 119 STANDBY 18 MU-0040PT LET-DOWNITDW 302461-1 AUXIUARY S IN USE Y VBDP-9 3 173 TRANSMITTER 119 IN USE 169 18 MU 004 LET-DOWN FIDW 302461-1 AUXIUARY~ S IN USE Y VBDP-18 0R DFTl TRANSMTFTER I19 IN USE VBDP-5 25 171 19 MU405-TE LETDOWN LINE TEMPERATURE 302461-1 AUXIUARY S IN USE Y VBDP-5 25 I19 IN USE Appendix B 43

y- p..

SEQ T CL . ID NO EQUIP DESCR!rTION DRAWING BLIMP EVAL ' SSELNOTE NORMt -PWR SUPORT DW INTERCol48 3 EL messern

-810 18 MLW7 RCP3AI SEALINJECT10N 302 461-3 REACTOR S IN USE Y VBDP-I S OR DPTl FLOW TRANSMITTER I19 IN USE . W-5 25 811 18 ML W 7- REP 3A2 SEAL DUEC110N FLOW 302461-3 REACTOR 3 IN UEE Y VBDr.l g CR DFT2 TRANSMITTER 119 IN USE VBDP-5 25 18 MU407- RCP3BI SEALINJEC110N 302461-3 REACTOR S M USE Y gDP-t s OR 812

• DFT3 FLOW TRANSMITTER 119 IN USE VBDP-3 25 18 MU4o7- RcP 3B2 SEALINJECI1ON 302461-3 REACIOR S IN USE Y- VBDP-I S OR 813 DFT4 FIDW TRANSMIITER g39 IN USE VBDP-325 162 0 W12-FT MAkE-UF FLOWTRANSMITTER 302461-2 AUXIUARY $ IN USE Y ACDP-518 119 IN USE 7 m 12 MUV-108 CONTROL 302461-2 AUXIUARY S IN USE Y IA 741 POC 119 IN USE 18 MU-014-LTI MAAE-UP TANK LEVEL 302 4 61-2 AUXIUARY s IN USE Y VBDP-8 3 121 TRANSMITTER 119 IN USE 122 18 MU414-LT2 MAKE-UP TANK LEVEL 302 4 61-2 AUXIUARY S IN USE Y VBDP-10 3 TRANSh M R I19 IN USE 729 7 MU415 MUV-16 cottrROL -

302 461-1 AUXIUARY S IN USE Y gr POC 095 IN USE 34 8B MU415-SV MUV-16 AIR FAIL LOCK MU54,308- AUX 1UARY S STANDBY Y VBDP4 23 830 095 STANDBY

! 123 X 18 MU-017-PT M AhE-UP TANK PRESSURE 30246l-2 AUXIWARY S IN USE Y VBDP-I 8 OR TRANSMITTER 119 IN USE VBDP-3 25 143 18 MU4I8-DPT LET-DOWN FILTER DELTA-P 302461-2 AUXIUARY S IN USE Y VBDP4 25 TRANSMflTER I19 IN USE OR VBDP-7

- 18 l

l Appendix B 44 l

l ___ _ ______ _ ___ __ _ __ _ __-_____-_ _ _-__ _ _ _ ____ _ _-_____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - , . _ _ _ _ _ _

p .

J %Y seq Y CL- ID NO EQUIP DESCRilmON DRAWING REDGf EVAL SSEL NOTE NORMf PWR SUPORT DW INTES N MS '

R N EI. Am la MU423- - M PRESS DUECllON FIDW 302 4 14 AUXIUARY S M USE Y RCm 22 FOWER DFTl IDOP B-1 095 IN USE MU423- HI PRESS DUECTION FIDW 302 4 1-3 AUXIUARY g M USE Y RCITS-A 23 13 DFD 1DOP A-2 095 IN USE 13 MU423- W PRESS DUECTION FIDW 30241-4 AUXIUARY S IN USE - Y RCIT3-B 24 POWER "DFD IDOP B-2 095 W USE la MU423- M PRESS DUECTION FIDW 302461-3 AUXIUARY S IN USE Y RCETS-B 25 FOWER DFT4 IDOP A-1 093 IN USE la MU423 M PRESS INJECTION FIDW 302 4 61-4 AUXIUARY S IN USE Y REMOTE  !

26 DFT5 IDOP B 095 IN USE N RELAY ACT -

CHANNELA I POWER r 1g MU-023- HI PRESS INJECTION FLDW 302461-3 AUX 1UARY S N USE Y REMOTE 27 DPT6 LOOP A 095 IN USE N RELAY ACT

• CHANNELA  !

POWER 13 MU423- M PRESS DUECTION FIDW 302 4 61-4 AUXIUARY S IN USE Y REMOTE 23 DFT7 IDOP B 095 IF USE - SHUTDOWN RELAY ACT CHANNEL B 1g MU423- HI PRESS INJECTION FLOW 302461-3 AUXIUARY S IN USE Y REMOTE l 29 DPTS . IDOPA 09$ IN USE SHUTDOWN i RELAY ACT  ;

CHANNEL B l

l MU-024-DFT . MAKE-UP FLOW TRANSMITTER 30246l-3 AUXIUARY S IN USE Y VBDP-9 3 .

i 42 18

! 095 IN USE l

i Appendix B 45 M __ _ _ ___ _ _ __._._u +, m-__-_ m._ _._ _r , _ , r- - s. _.-- + _ ,

. _ . m . _

m

~

/ d seq T CL- to NO EQUIP DESCRWTION DRAWING . BEEGI EVAL SSELNOTE ' NORW .FWR SUPORT WW INTEREONS R-y EL namern i

43 'la MU424- MAKE UP FIDWTRANSMITTER 302 4 61-3 AUXILIARY S . IN USE Y VBDP4 25 i

DPT2 095 IN USE OR VBDP-7 la.

730 7 MU425 MUV-31 CONTROL 306430 AUXILLARY g - IN USE Y IA N

095 ' IN USE ~

35 88

• MU4254V MUV-31 AIRFAILIDCK MU54. 308- AUXILLARY g ' STANDBY- Y VBDP4 23 8# 095 STANDBY 30 13 MU427-DPT RCPTOTALSEALINECTION 302461-3 AUXILLARY S IN USE Y VBDP-18 OR -

FIDW TRANSMf!TER 095 IN USE VIM)P-5 25 806' 18 MU431-FTI RCP3AI SEAL RETURN FLOW 302461-2 REACTOR S IN USE - Y VBDP-I ll ,

TRANSMITTER 119 IN USE OR VBDP-5 7 807 18 MU431-FT2 RCP 2A2 SEAL RETURN FIDW 30246l-2 REACTOR S IN USE Y Y VBDP-1 1I ,

TRANSMITTER I19 IN USE OR VBDP-S 7 808 18 MU-031-FT3 RCP 3BI SEAL RETURN FIDW 302461-2 REACTOR S N USE .Y . VBDP-111 .r TRANSMITTER 119 IN USE . OR VBDP-S 7 '

=

809 18 MU431-FT4 RCP3B2 SEAL RETURN FIDW 302 4 61-2 REACTOR S IN USE Y VBDP-l 11 TRANSMITTER 119 IN USE OR %E*-5 7

• 170 13 MU4sI-DPT LET-DOWN PRE-FILTER DELTA- 302461-1 AUXILLARY S IN USE Y VBDP-1 1 OR PTRANSM N 119 IN USE VBDP-S 11 728 1g MU-102-DPI RCP SEALINECTION FILTER 30246I-3 AUXILLARY N IN USE N N/A DELTA-PINDICATOR 095 IN USE 21 MUDM-IA MAEUP AND PURIFICATION 302461-1 AUX 111ARY S IN USE N 153 N/A.

DEMINERAI17FR IA 339 IN USE I

21 MUDM-IB MAKE-UP AND PURIFICATION 302 461-1 AUXILLARY $ IN USE N N/A 154 '~

DEMINERAllZER IB yg9 IN USE Appendix B 46 t

r s- p s, b U d SEQ T CL ID NO EQUIP DESCRIPTION DRAWING BLDG / EVAL SSEL NOTE NORMI P%1L SUPORT DW INTERCONS R

g EL nessern ET-DOWN COOER 3A 3024 61-1 REACIOR N USE N SW '

490 A 21. MUHE-IA S 095 IN L5E 491 X 21 MUHE-1B LET-DOWN COOLER 3B 302 461-1 REACTOR S IN USE N SW 095 IN USE MUHFIC ET-DOWN COOER 3C REACTOR N USE N SW 492 A 21 302 461-1 S 095 IN USE 21 MUHE 2A RCP SEAL RETURN COOER 3A 30246l-2 AUXILLARY S IN USE N SW 126 119 IN USE 127 21 MUHE-2B RCP SEAL RETURN COOER 3B 30246l-2 AUX 1UARY S N USE N SW 119 IN USE 7 A 5 MLT-IA klAKE-UP AND FURIFICATION MU-1,302 AUXIUARY S OFF Y DPDP-4A 10 PUMP 3A 661-4 302- 095 ON AND MTSW.

631-1 2D 8 AB 5 MUP-1B MAk.E-UP AND PURIFICATION MUO2, AUXILLARY $ IN USE Y MUXS-1 PUMP 3B MUO3. 302- 095 IN USE AND DPM-661-4 SA 10 OR DPDP-5B 10 5 MUP-IC MAKE-UP AND PURIFICATION MUO4,302- AUX 111ARY $ OFF Y DPDP-5B 10 11 B PUMP 3C 661-4 302- 095 ON AND MTSW.

631-2 2F 9 A 5 MUP-2A MUP-I A MAIN OIL PUMP MUO5 AUXILLARY S OFF Y MTMC-4 SA 095 ON 12 AB 5 MUP-2B MUP-1B MAIN OIL PUMP MUO6 AUXILLARY S N USE Y MTMC-7 2B 095 IN USE 13 B 5 MUP-2C MUP-1C MAIN OIL PUMP MUO7 AUX 111ARY S NT Y hfIllC-5 4C 095 ON MUP-4A MUP-1 A GEAR 011' PUMP MU0S AUXILIARY OFF Y 10 A 5 S MT11C-4 3C 095 ON Appendix B 47

i g ~g g j

's SEQ T CL IDNO EQUIP DESCRIFTION DRA%1NG BLDGI EVAL SSEL NOTE NORW PWR SUPORT DW INTERCONS R

y EL Drman l

14 AB 5 MUP-4B MUP-1B GEAR OIL PUMP MUO9 AUXIUARY S IN USE Y MTMC-7 2C .

095 IN USE 15 -B 5 MUP-4C MUP-IC GEAR OIL PUMP MU10 AUXIMARY S OFF Y MTMC-5 3D 095 ON 125 X 21 MUT-1 MAKENPTANK 302 4 1-2 AUXIUARY S N USE N N/A 119 IN USE 839 N/A MUV-014 MAKEUPPUMPS ISOLATION 302461-3 AUXIUARY N OPEN N VALVETO RCP SEALS 095 OPEN 840 N/A ilUV415 MAKEUP PUMPS ISOLATION 3024 61-3 AUXILIARY N OPEN N N/A VALVETO RCP SEALS 095 OPEN 31 7 MUV-016 RCP SEALINJECTION FLOW MU54,302- AUXILIARY S IN USE Y VBDP-6 23, CONTROL VALVE 661-3 095 IN USE IA 841 N/A MUV-017 MUV-16 BYPASS VALVE 302 461-3 AUXILIARY N CLOSED N N/A 095 OPEN 163 8A MUV-Ols RCPSEALISOIATION VALVE 302 4 61-3, AUXIUARY S OPEN Y MTMC-7 2D W 23 119 OPEN 36 8A MUV-023 IIPINJ CONTROL VALVE TO 30246I-3 AUXILIARY S . CLOSED Y MTMC-3 RCS INLET UNES LOOP A , ES-A27. MU- 095 OPEN 6BLIOR 23 MTMC-22 IBDR 37 8A MUV-024 HPINJ CONTROL VALVE TO 302461-3 AUXIUARY S C1DSED Y MTMC-3 RCXINLET LINES LDOP A 095 OPEN 6MI OR MTMC-5 SCRI 38 8A MUV425 IIPINJ CONTROL VALVE TO 302461-4, AUXILIARY S CLOSED Y MTMC-22 RCS INLET UNES LOOP B ES-B27. MU- 095 OPEN - 2BDR OR 21 MTMC-3 6BL2 Appendix B 48 e . . . _ - _ - _ _ _ _ _ - _ _ - _ _ _ _

l SEQ T CL D NO EQUlf DESCRIPTION pstA%1NG BLDGf EVAL SSEL NOTE NORM / FHM SUPORT UW INTERCONS i .R g EL DESIRED l

44 8A MUV426 HPINJ CONTROL VALVETO 302461-4 AUXIUARY S CIDSED Y MD4C 5 RCS DHT UNESIDOP B ES-B27 MU- 095 OPEN SCR2 OR 22 MDec-3 6BR2 ,

l 39 8A MUV-027 HPICONTROLVALVE TO RCS 302 4 61-3 AUX 1UARY S OPEN Y MTMC-73C 1 DOPA ES-abo t* 095 CIDSED MU-16 7 MUV-031 MAKE-UP FIDW CONTROL MU54,302- AUXIUARY S IN USE Y VBDP4 23 32 i VALVE 66l-3 095 IN USE 3A 829 N/A MUV434 BYPASS ISOLATION VALVETO 30246l-3 AUXIUARY N CLOSED N. N/A RCP SEALS 095 OPEN 830 N/A MUV-035 BYPASS ISOLATION VALVETO 302461-3 AUXILIARY N CIDSED N N/A RCP SEAIS 095 OPEN 33 7 MUV449 LET-DOWN FIDW ISOLATION hRD3,302 AUX 1UARY S OPEN Y prpP-SB 20 VALVE 661-1 095 OPEN IA 40 8B MUV449- MUV-49 CONTROL MU33 AUXIUARY S Y DPDP-88 20 SV 095 151 7 MUV-050 LET-DOWN BIDCK OROFICE MU33,302- ALDGUARY S OPEN Y ACDP-Si t j ISOLATION VALVE 661-1  !!9 OPEN ANDIA l 120 8B MUVan MUV-50 COrGROL MU33 AUXIUARY S Y ACDP-SI I SV 3ng 152 7 MUV45i LET-DOWN FLOW CONTROL MU54,302- ALOGUARY S CONTROL Y VBDP-6 23 VALVE 66l-1 119 CONTROL ANDIA 62 8A MUV45 HI PRESS INJECTION SUCTION 302461-4 AUXILIARY S CIDSED Y MTMC-22 9B FROM BWST ES-B27. MU- 095 OPEN 17 Appendix B 49

'T

's s w v SEQ T CL ID NO EQUlF DESCRIFTION pgAwgNG BLDCI EVAL _ SSELNOTE NORM / FWR SUPORT DW INTEREDNS y EL Drstaan

-% 8A MUV473 BWSTTO MUP-I A & MUP-IB MUlt 302- AUXILLARY s CIDSED Y MTMC-21 ISO 1ATION VALVE 661-4 095 OPEN 10F ,

13g 7 MUV490 LETDOWN FIL1ER MUFIrlBTO 302461-2 AUXILLARY s OPEN Y ACDP-52 5, nRTF-1 ISO 1ATION VALVE MU 42 119 OPEN IA IITDOWN FILTED MLEIATO 302461-2 OPEN Y ACDP-517, 139 7

• MUV491 MUT-1 ISOIATION VALVE MU 42 AUXIUARY 119 s

OPEN IA 140 7 MUV-096 IITDOWN FILTER MLEIA 302-661-2 AUXILLARY s OPEN Y ACIh .517 INLETISOLA' DON VALVE MU-41 I19 OPEN IA 141 -7 MUV497 IITDOWN FILTER MUFLIB 302461-2 AUXILLARY s OPEN Y. ACDP-52 5 INLETISOIATION VALVE MU-41 119 OPEN IA 8A MUV-100 MUFIrl A/MLTIrlB BYTA$s 302461-2, AUX 1113Y ' s CIDSED Y MTMC-4 98 142 VALVE MU42 119 CLOSED 7 MUV-103 BORIC ACID PUMPTO MAkF UP 302461-2 AUXILLARY s CLOSED N IA 1%

TANK ISOLA 110N VALVE I19 OPEN 160 8B MUV-103- MUV-103 CONTROL MU36 ALMY s Y ACDP-51 I sV gg, 7 MUV-108 BORIC ACID PUMPTO MITT-1 302-661-2 AUXILIARY s CLOSED N IA 157 t FLOW CONTROLVALVE I19 CONTROL ,

8A MUV-112 LETDOWN TO MUT-1 OR WD MUIS,302- AUXILLARY s TO MUT-1 Y MTMC-3 98 161 DIVERTER 661-1 119 TO MUT-1 182 7 MUV-116 DEMINERAllZER MUDM-IA 302-661-1 AUXILLARY s OPEN Y ACDP-517 ISOLATION VALVE TO MU-39 122 OPEN IA LETD0%W FILTER L

Appendix B 50 m_- _ - _ . - - _ - - - - - - - - _ -- - _ - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - - _ - _ . - -

,, .\

b b \I SEQ T CL IDNO EQL1F DESCRIPTION DRAWING BLDG / EVAL SSEL NOTE .N PWR SUFORT IpW INTERCONS R

N EL . Wam 183 7 MUV-117 DEMINARAI 17FR MUDM-1B 302461-3 AUXILLARY g OPEN Y Acor.52 5, ISOLATION VALVE TO MU-40 122 OPEN IA IITDOWN FILTER 188 7 M UV-124 IsOuTION VALVETO 30241-1 AUXIUARY S OPEN - Y ACDP-517 FLitlFICATION MU-38 124 OPEN IA DEMINERAI17FR MLDM-I A 190 7 MUV-133 ISOIATION VALVE TO 302461-1 AUXIUARY S OPEN Y ACDP-52 5 DEMINERAI17FR MUDM-1B MU-39 124 OPEN IA 184 8A MUV-194 MUFL-2A%4UFL 2B BYPASS 302461-1 AUXIUARY S CIDSED Y MTMC-410D VALVE MU43 123 C1DSED 189 7 MUV-200 LETDOWN !SOIATION VALVE 302461-1 AUXILLARY S OPEN Y ACDP-52 5 TO DEMINERAI17Fe MUDM-1A M 124 OPEN M 192 7 MUV-20I LETDOWN ISOLATION VALVE 302461 1 AUXIUARY S OPEN Y ACDP-517 TO DEMINERAI 17FR MUDM-1B 128 OPEN IA 185 7 MUV-242 PREFILTER MUIL2AINLET 302 461-1 AUXIUARY g OPEN Y ACDP-517, ISOLATION VALVE MU-34 123 OPEN IA 180 7 MUV-243 PREFILTER MUF1,2A -

302461-1 AUXIUARY g OPEN Y ACDP-517 DISCHARGE ISOIATION VALVE 121 OPEN IA 181 7 MUV-244 PPEFILTER MUFle2B 302 461-1 AUXIUARY S OPEN Y ACDP-52 5 DISCHARGEISOLATION VALVE MU-35 121 OPEN IA 136 7 MUV-245 PREFILTFR MUFI,2B INLET

- 302 4 61-1 AUXIUARY $ OPEN Y ACDP-52 5

' ISOIATION VALVE MU-34 123 OPEN IA 166 7 MUV-253 REACTOR COOLANT PUMP 302461-2 AUXILIARY S OPEN Y DPDP-5B 22 SEAL BLEEDOFFISOLATION ES-B54, MU- IA 119 CIDSED VALVE 44 Appendix B 51

Ip\

-]  %

(

(-)

NJ SEQ T CL ID No EQUIF DESCRIFTION DRA%1NG BLDC/ EVAL $5EL NOTE NORM / PHR sUPORT DW INTERCONS R

N EL DESIRED MU SYSTEM TO PZR AUX 302461-3 AUXILLARY N "m N N/A 882 N/A MUV-273 SPRAY ISOLATION VAL \T 130 OPEN N/A MUV 453 SEALINJECT10N MLE3A 302461-3 AUXILIARY N C1DSED N N/A 831 INIITISOLATION VAL \T 095 OPEN N/A MUv-454 SEALINJECTION MUL3A 302 4 61-3 AUXILLARY N C1DSED N N/A 832 -

INLETISOIATION VALVE 095 OPEN SEALINJECTION MUL3A 30246l-3 AUXILLARY """ N/A 833 N/A MUV-455 N .N OUTIITISOLATION VALVE 095 OPEN 834 N/A MUV-456 SEALINJECTION MUL3A 302461-3 AUXILIARY N CIDSED N N'A OUTIITISOLATION VALVE 095 OPEN 835 N/A MUV-457 SEAL INJECTION MUFL-3B 30246l-3 AUXILIARY N C1DSED N N/A INLETISOIATION VAL %I 095 OPEN N/A MUV-458 SEALINJECTION MUFI,3B 302461-3 AUXILIARY N C1DSED N N/A 836 IN1ETISOLATION VAL \T 095 OPEN N/A MUV-459 SEALINJECTION MUFIA3B 302 461-3 AUXILLARY N CLOSED N N/A' 837 OUTLETISOLATION VAL % 095 OPEN N/A MUV 460 SEALINJECTION MUF13B 302461-3 AUX 111ARY N C1DSED N N/A 838 OUTLETISOLAllON VALVE 095 OPEN 481 X 3 MUXS-l 4160VISOLATION S%TTCH 206411 AUXILIARY s EITHER N N/A 095 EITHER 21 NGT-XX ADV BACKUP NITROGEN 302 4 73-2 TURBINE S STANDBY N- N/A 453 SUPPLY TANKS (10) 095 IN USE 18 NGV-299 ADV BACKUP NIdOGEN 302473-2 TURBINE N CLOSED N N/A 732

• SUPPLY VALVE 095 NED Appendix B 52 n---------------------_-_----------------------_---__-_----------------- - .

.. -- m U_ O U(%

SEQ T CL' ID NO ~ EQUIP DESCRIPTION - DaA%1NG BLDGt EVAL. SSELNOTE NORM / PWR SUPORTIrW INTERCONS

" namnrn 3 Et 733 13 NOV-308 ADV BACKUPNITROGEN 3024 73-2 TLitBENT N- Cs mn N N/A SUPPLY VADT 095 OPEN -

853 N/A NOV-312 ADV NTTROGEN BACKUP 302 4 73-2 TURBINE N C1) DEED N N/A ISOLA 110N VALVE 095 OPEN 354 N/A NOV-324 NITROGEN HEADER VENT 302472-2 TURBINE N OPEN N VALVE 095 N 697 20 NBAP-Al. NIAPSYSTEMSUBASSEMBLY A CONTROL S N/A N CABMET I I45 WA 698 20 NIAP-A2 NIAP SYSTEM SUBASSEMBLY A CONTROL .S N/A - N CABMET2 145 N/A 699 20 Ni&P-B1 NIAP SYSTEM SUBASSEMBLY B CONTROL 5 MA N CABEET I I45 N/A 700 20 NIAP-B2 NIAP SYSTEM SUBASSDIBLY B CONTROL S N/A N CABEET 2 145 N/A 701 '20 Ni&P41 NIAP SYSTDISUBASSEMBLY C CONTROL 5 NA N CABWET I 145 N/A 702 20 NIAP42 NIAP SYSTEM SUBASSDiBLY C CONTROL S N/A. N CABWET 2 145 WA 703 20 NIAP-DI NIAP SYSTEM SUBASSEMBLY D CONTROL S N/A N CABW Ul 145 N/A 704 20 NIAP-D2 NIAP SYSTEM SUBASSEMBLY D CONTROL S N/A N .

CABMET 2 145 N/A l .. 757 20 NI-t-A3 PROPORTIONALCOUNTER E-2176 REACTOR S IN USE . Y VBDP-317 ASSEMBLY I40 IN USE l

, Appendix B 53 l

,~s pm (m.

>J

)

.Nd

( ).

SEQ T CL IDNO EQUlr DESCRIPTION DgAw1NG BLDGl EVAL ; SSELNOTE NOEUW FWR SLTORTDW INTERCOM 5

." EL DESERED _t NI-2 m PROPORTMAL COUNTER E-2176 REACTOlt M USE ~Y VBDP417 758 20 S ASSEMBLY 140 N USE 759 20 EM COMPENSATEDION E-2177 REACTOlt . S M USE Y VBDP-517 CHAMBER / ASSEMBLY H0 M USE COMPENSATEDION REACTOR IN USE Y VBDP417 760 20

• NI4 M CHAMBER / ASSEMBLY E-2177 S I40 ' IN USE 705 20 NNI-1 AUWARY COMOL SYSTEM W NTROL S CABENET 1 343 706 20 NNI-2 AUXILIARY CONTROLSYSTEM CONTROL S CABNET 2 343 707 20 NNI-3 AWilARY CONTROLSYSTEM CONTROL S CABMET 3 g43 708 20 hW AUXILJARY CONTROLSYSTEM CONTROL S CABMET 4 343 709 20 NNI-5 AUX 112ARY CONTROLSYSTEM CONTROL $

CABINET 5 g43 710 20 NN14 AUXILLARY CONTROLSYSTEM CONTROL S CABINET 6 g43 711 20 NNI-7 AUXILIARY CONTROL SYSTEM CONTROL S CABINET 7 343 712 20 NES AUXILIARY CONTROL SYSTEM CONTROL S CABINET 8 145 482 20 NSP NUCLEAR SAMPLE PANEL AUXILLARY S N/A N 093 ._ N/A Appendix B 54 F . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ __ .- ___ -- ___ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . . _ _ . . . _ _ . _ _ _

n T

- .- w --T1. B_l- .- - -- -- T- .--

N EL Bemm 532 20 FOItV/ TEMP FORV& TEMPERA 1URE CONTROL S N/A N SATURATION CABENET 105 ' N/A -

.734 13 . RCeol-LTI PRESSURIZER MVEL 302 4 51-1 REACTOR S IN USE 'Y. VBDP43 1RANSWTTER 095 IN USE IN USE Y

-735 ' 13 - RC4ol-LT2 PRESSUltIZER TRANSMITTER LEVEL 302 4 51-1 REACTOIt S VBDP-18 OR N525 095 IN USE 786 13 RC401-LT3 FItESSURf7FR E VEL 302451-1 REACTOR S IN USE Y \h10 3 N 095 IN USE 646 19 RC402-TEI FRESSURIZERTEMPERATURE 30245I-1 REACTOIt S IN USE N 139 IN USE 647 19 RC-002-TE2 PRESSURIZERTEMPERATURE 302451-1 REACTOR S IN USE N 139 IN USE 1

797 13 RC403A- ' REACTOR COOLWTSYSTEM 302 4 51-1 REACTOR S N USE Y VBDP-317 -

PTl PRESSURE TRANSMTTER 095 IN USE 793' 13 RC-003A- REACTOR COOLANTSYSTEM 302451-1 REACT 91t S IN USE Y ' VBDP-517 PT2 PRESSURETRANSMITTER 095 IN USE 799 13 RC403A- REACTOR COOLANT SYSTEM 302451-1 REACTOR S N USE Y \1BDP-3 21 FT3 PRESSURE TRANSMITTER 095 IN USE 800 13 RC-003A- REACTOR COOLANTSYSTEM 302 4 51-1 REACTOR S IN USE 'Y \11DP-521 FT4 PRESSURE TRANSMITTER 095 IN USE 801 18 RC403B- REACTOR COOLANT SYSTEM 302 451-1 REACTOR S N USE Y g1 gor.417 FIl PRESSURE 11tANSMITTER 095 N USE 802 18 RC403B- REACTORCOOL,WTSYSTEM ' 302451-1 REACTOR S N USE Y 51BDP417 FT2 PRESSURE TRANSMITTER 095 IN USE e

Appendix B 55

- - . _ _ _ . _m ._ . _ _ . . _ . . _ m _ ..

~

p ],

i Y' J l -- sEn T CL In NO EQUIF DESCRIFTION DRAWING BLDCf EVAL S$ELNOTE NORlw FWR sUFORTWur INTEREDNE R-3 RL- nresern

~803 13 RC403B- REACTOR COOLANT SYSTEM 302451-1 REACTOR S M USE . Y VBDP4 21 PT3 PRESSURETRANSMITTER 995 IN USE 314 19 RC404A- REACTOR COOLANT SYSTEM 302451-1 REACTOR S IN USE - N 1TI HOTMG ATEMPERAlVRE I19 IN USE ,

815 19 RC404A- REACTOR COOLANTSYSTEM 302451-1 REACTOR S N USE N

• TE2 HOTLEO ATEMPERATURE I19 IN L5E 816 19. RC404A- REACTOR COOLANTSYSTEM 302451-1 REACTOR S IN USE N TE3 HOTMO ATEMPERATURE I19 IN USE 817 19 RC404A. REACTOR COOLANT SYSTEM 301451-1 REACTOR S IN USE N .

TE4 HOT LEO A17MPERAltitE I19 IN USE 713 19 RC 004B. REACTOR COOLANT SYSTEM 302451-1 REACTOR S IN USE N TEI HOT LEG BTEMPERATURE I19 IN USE 818 19 RC-0048- REACTORCOOIAlff SYSTEM 302451-1 REACTOR S IN USE N TE2 HOT EO B TEMPERATURE 119 IN USE 819 19 RC404B- REACTOR COOLANTSYSTEM 302451-1 REACTOR g IN USE .N TE3 HOT LEG B TEMPERATURE yg9 IN UEE 820 19 RC-004B. REACTOR COOLANT SYSTEM 302 451-1 REACTOR S IN USE N TE4 HOT EG BTEMPERATUltE 119 IN USE 821 19 RC-00$A- REACTOR COOtANT SYSTEM 302451-1 REACTOR S IN USE N TER COLD MG ATEMPERATURE I19 IN USE 822 19 RC405A- REACTOR COOIANT SYSTEM 302 4 51-1 REACTOR S IN USE N TE2 COLD LEG B TEMPERATURE g39 IN L5E i

823 19 RC-005A- REACTOR COOIANT SYSTEM 30245l-1 REACTOR S IN USE N TE3 COLD LEO BTEMPERATL1tE 119 IN L5E i

Appendix B 56

m O .

%J

-SEQ T CL ID No EQUIP DESCRIFDON DRAWING BLDG / EVAL SSEL NOTE . NORMI P%?- SUPORT BW INTERCOME R

y EL Demmen 824 19 RC405A- REACTOR COOLANT SYSTEM 3024 51-1 REACTOR .S IN USE N TE4 COID EO ATEMPERATURE I19 IN USE i 825 19- RC405B. REACTOR COOLANT SYSTEM 302 451-1 REACTOR S- IN USE N TER CXMD LEO BTEMPERATURE I19  : E USE 826 19 RC405B. REACTOR COOLANTSYSTEM 302 451-1 REACTOR S M USE N

• TE2 CXMD LEO B TEMPERATURE I19 IN USE 827 19 RC405B- REACTOR COOLANT SYSTEM 302451-1 REACTOR S IN USE N TE3 CULD LEO BTEMPERATURE I19 M USE 828 19 RC405B- REACTOR COOlANTCOID EG 302451-1 REACTOR S IN USE N TE4 B N TURE I19 IN USE 789 18 RC-014A- REACIORCOOLANT SYSTEM 3024 51-1 REACTOR S M USE Y VBDP-317 DFTI HOTEO AFLOW 095 IN USE 790 18 RC414A- REACTOR COOIANTSYSTEM 302 4 51-1 REACTOR S IN USE - Y VBDP-417 DPT2 HOT EO A FLOW 095 M USE 791 13 RC414A- REACTOR COOLANT SYSTEM 302 4 51-1 REACTOR S IN USE Y VBDP-517 DPT3 HOT LEO A FIDW 095 IN USE 792 13 RC414A- REACTOR COOIANT SYSTEM 302451-1 REACTOR S IN L5E Y VBDP417 DPT4 HOT EO A FIDW 095 IN L5E 793 18 RC-014B- REACTOR COORANT SYSTEM 302 451-1 REACTOR S IN USE Y \13DP-317 DFTI HOT EO B FLOW 095 IN USE 794 18 RC 014B- REACTORCOOLANT SYSTEM 302451-1 REACTOR .S IN USE - Y VBDP-417 DPT2 HOT LEO B FLOW 095 IN USE i

795 18 RC414B- REACTOR COOLANT SYSTEM 3024 51-1 REACTOR S IN USE Y \130r-517 DPT3 HOT LEO B FLOW -

095 IN USE Appendix B 57 n--_------ - - _ - - - . - - _ _ _ - - - - - _ _ - - _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _. . . . _ . _ . _ _ _ _. - _ . _ _ _ _ _ _ _ _

-~ -

'V

\ /.

Ssq T CL ID NO EQUIP DESCRIPTION DRAWING BLDGf EVAL : SSELNOTE NORAS/ PWR StJPostT DW INTERCOfES R

EL Nn N

~

796 18 RC4148- REACIOR COOLANT SYSTEM 3024 51-1 REACTUst s M USE Y VgDP4tT

. DFT4 HOTLEO B FLOW 095 -- IN USE -

j l.

I 787 18 RC-131-FT REACIDR COOtANT SYSTEM 302 451-1 REACTOR '

S M UBE Y VBDP410 j PRESSURE 095 IN USE OR VEP-7

l. 17

.788 18

• RC-131-FTl REACIDR COOIANT SYSTEM 302451-1 REACIDIt S M USE Y VBDP-3 s OR -

PsESSURE 095 IN USE VBDP-3 25

-571 20 ' RCCP-I PRESSURIZER HEATER SCR INTER S . N/A N CONTREPANEL I19 N/A 622 20 RCITS-A REACTOR COOIJLNT CONTROL -S N/A N MNY N 124 N/A SYSTEM CABINET A 623 20 RCITS-B REACTOR COOIANT CONTROL. S N/A N MNY N 824 N/A SYSTEM CABINET B 624 20 RCITSC REACTOR COOLANT CONTROL S N/A N MTNTORY TRACM 124 N/A .

SYSTEM CABINETC 533 20 RCPM-3A REACTOR COOLANT PUMP CONTROL S N/A N POWER NORNG CABMET 108 'N/A A

534 20 RCPM-3B REACTOR COOLANT PUMP CON 11tOL S N/A N POWER MONITORING CABIhTT 108 N/A B

572 20 RCTR-! RCP-IC TRANSFORMER INTER S N/A N CABINET g39 . gjg Appendix B 58 n - . - _ - -

n ~

n' p seq T CL 13 NO EQUlF DESCRIFTION DRAWINc BLDGI EVAL SSELMOTE NORM / P%R SUFORT DW INTERO3NS R

N EL DESIRED 20 RCTR-2 RCF-IDTRANSFORMER lhTER S N/A N 573 CABINET 119 N/A-552 20 RCTR-3 RCP-IATRANSFORMER AUXILIARY S. . N/A - N N ET 119 N/A' i

20 RCTR 4 RCP-1B TRANSFORMER INTER S N/A N 574 '

N 119 N/A ,

8B RCV-10 PRESSURIZER FOWER RC13,25.27 REALTOR S C1DSED Y DPDP-48 I 765 OPERATED RFIIFF VALVE 302 451-1 gg g 648 BA RCV-Il PRESSURIZER BIDCK VALVE RCl3. 302- REACTOR S OPEN Y MTMC73A 651-1 168 OPEN 716 8A RCV-13 PRESSURIZERINLET 302 4 51-1, REACTOR S CLOSED. Y MTMC-7 '

AUX 111ARY SPRAYISOLATION RC14 145 OPEN VALVE 717 8A RCV-53 DH TO PRESSURIZER RC16,302- REACTOR' s CIDSED Y MTMC-7 5B AUXILIARY SPRAY ISOIATION 65l-1 145 OPEN VALVE 714 20 RFL MPLXR RFL MULTIPLEXER FOR 500 KV CONTROL S N/A N SWITCllYARD 145 N/A 715 20 RNR RECORDER NEST RACK CONTROL S N/A N 145 N/A 625 20 RR-HV AUXILIARY RELAY RACK CONTROL S N/A N HEATINO AND VENTIIATION 124 N/A 62- 20 RR-PSA AUXIUARY RELAY RACK CONTROL S N/A N 124 N/A 627 20 RRI AUXILIARY RELAY RACK CONTROL S N/A N

~

I24 N/A Appendix B 59 R ___ _ _ _ _ _ _ _ _ _ _ _ _ _ . . - _ _ _ _ ___ _ _ .__ _ _ _ .

N kJ .,

-SEQ Y CL ID NO EQUIF DESCRIPTION DRA%1NG BLDG / EVAL SSELNOTE NORM / F%R SUFORT DW INTERCONS R

g EL sarssman 628 20 RRIA- ENGINEERED SAFEGUARD CONTROL s N/A N AUXIUARY REIAY RACK RRIA 124 N/A 629 20 RRIAB ENGINEERED SAFEGUARD CONTROL s N/A N AUXIUARY REIAY RACK 124 N/A RRlAB 630 20

• RRIB ENGINEERED SAFEGUARD CONTROL s N/A- N AUXIUARY REIAY RACK RRIB 124 N/A 631 20 RR2 AUXIUARY REIAY RACK CONTROL s. N/A N 124 N/A 632 20 RR2A ENGINEERED SAFEGUARD CONTROL 3 N/A - N AUXIUARY REIAY RACK RR2A 124 N/A 633 20 RR2AB ENGINEERED SAFEGUARD CONTROL S N/A N AUXIUARY REIAY RACK 124 N/A RR2AB 634 20 RR2B ENGINEERED SAFEGUARD CONTROL s N/A N AUXIUARY REIAY RACK RR2B 124 N/A 635 20 RR3 AUXIUARY RELAY RACK CONTROL S N/A N 124 N/A 636 20 RR3A ENGINEERED SAFEGUARD CONTROL S N/A N AUXIUARY REIAY RACK RR3A ' 124 N/A 637 20 RR3B ENGINEERED SAFEGUARD CONTROL s N/A N AUXIUARY RELAY RACK RR3B 124 N/A 638 20 RR4A POST-ACCIDENT hlONITORING CONTROL S N/A N PANEL 4A 124 N/A 639 20 RR4B POST-ACCIDENT hlONITORING CONTROL S N/A N PANEL 4B 124 N/A Appendix B 60 w A ___ _ - + _ - . _ - _ - _ - _ - _ . _ _ . _ - - . - _ - _ - . _ . - -

T.

7- - (~s hwI ' .

SEQ T . CL - ID NO EQUlf DESCRIPTION DRA%1NG BLDC/ EVAlo SSEL NOTE .N FWR SUFORT DW INTERCONS R

N EL pum 640 20 RR5BI ENGINEERED SAFEOUARD CONTROL 5 N/A N AUXIIJARY RELAY RACK 124 N/A RR$BI 641 20 RR$B2 ENGINEERED SAFEGUARD CONTROL 3 N/A N AUXILLARY RELAY RACK 124 N/A RR$B2 535 20 RSA REMOTE SHUTDOWN RELAY CONTROL 5 N/A N CABINET A 108 N/A 536 20 RSki REM 01E SHUIDOHW REIAY CONTROL 5 N/A N N U A-l 108 N/A 537 20 RSACA REMOTE SHUTDO%H CONTROL 5 N/A N AUXIIJARY CABINET A 108 N/A 538 20 RSACB REMOTESHUTD0%W CONTROL S N/A N AUXILLARY CABINET B 108 N/A 539 20 RSB REMOTE SIRTfDO%W RELAY CONTROL S N/A N CABINET B 108 N/A 540 20 RSB-1 REMOTE SHUTDO%W REIAY CONTROL S N/A N NET &l 108 N/A 541 20 RSPA REMOTE SHUTDO%N PANEL- CONTROL s N/A N SECTION A 108 N/A 542 20 RSPAB REMOTE SHUID0%H PANEL- CONTROL S N/A N SECTION AB 108 N/A

543 20 RSPB REMOTE SliUTDOWN PANEL- CONTROL S N/A N SECTION B 108 N/A Appendix B '61

- . - ,< ._ . _ . . . - m. .__ _ . .. . _ . . . . _ _ _ ..m .. _ . .

C '*g .

. [%

N

SEQ T CL 13NO EQUIP DESCRIPTION DRAWING BLDG / EVAL SSEL NOTE NORMf FWR SUFORT DW INTEBCXNES ,

R ,

N EL DESERED 103' 13 ' RW48-FT DECAY HEAT SEAWATER 302411-1 AUXILLARY g. IN USE Y - VBDP-1 I OR FUMP B DISCHARGE PRESSURE 095 IN USE VBDP-5 II 94 13 . RW49 FT DECAY HEATSEAWATER 302411-1 AUXILLARY g. M USE Y . VBDP-2 i OR PUMP A DISCHARGE PRESSURE 095 IN USE - YEOP4 I4 '

, ~ ..

. 66 .19 RW-12-TE DH SERVICE SEAWATER FUMP 302411-1 AUXIUARY g ' IN USE Y; 17C ,

RWP-3B D SCHARGE 095 IN USE TEMPERATURE 63 19 RW-13-TE DECAY HEAT SEA WATER 302411-1 AUX 1UARY S M USE- Y TPC FUMP RWP-3A DISCHARGE I 095 IN USE TEMPERATURE 65 19 RW-19-TE NUC1. EAR SERVICE SEAWATER 302411-1 AUXILLARY S IN USE Y TPC FUMP RWP-2B DISCHARGE 095 IN USE TEMP 102 13 PW-23-rf NUCLEAR SERVICE SEAWATER 302411-1 AUX 111ARY S IN USE Y VBDP-11 OR PUMPS DISCHARGE PRESSURE 095 m USE VBDP-511 60 19 RW-32-TE DECAY HEAT COOLER DCHE- 302411-1 AUXIUARY S IN USE Y TPC IB SEA WATER OUTLET 095 IN USE i

61 19 RW-33-TE DECAY HEAT COOER DCHE. 302411-1 AUXIUARY S IN USE Y TFC IA SEA WATER OUTET 095 IN USE 73 19 RW-43-TE SEA WATER OUTLET NUCEAR 302 4 11-1 AUXIUARY S IN USE Y ' TFC .

SERVICE COOLERS 095 m USE 98 6 RWP-I NORMALNUCLEAR SERVICES 302401-3 AUXIUARY S ON N N/A .NONE  ;

SEA WATER PUMP MOTOR 095 OFF l COU.ER i 90 6 RWP-2A NtILEAR SERVICE SEA WATER RWO2,302- AUXILIARY S OFF Y ' DPDP.$A lo, ,

PUMP 3A 65 t-I 302- 095 ON . MTSW-2C 601-3

.Y Appendix B 62 -

.9~___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ __ ___ ,_ _ _ ____ __.__ __ - , , , . ~ . ,,, ,~ m,, , .~,

, _ . .. . _ . . _ .- = - - -. . .

% 2 ,

seq T CL .10NO EQUIP DESCRIFFION DRAWING BLDG # EVAL SSEL NOTE NORW PWR SUPORT DW INTERCONS y EL Dessern 6 RWP-2B NUCLEAR SERVICE SEAWATER RWO3,302- AUXHJARY S OFF .Y DPDP-5B 10 99 PUMP 3B 611-1 302* 095 ON AND W -

601-3 2E' 91 6 RWP-3A DECAY HEAT SERVICE SEA RWO4,302- AUXELARY S OFT Y DPDP-5A 10 WATER PUMP 3A 611-1 302- 095 ON AND MTSW-  :

631-1 2C

~

100 6 RWP-38 DECAY HEAT SERVICE SEA RWO5,302- AUXILLARY S OFY Y DPDP-5B 10 WATER PUMP 3B 611-1 302- 095 ON AND MTSW- i 631-2 2E 724 21 RWSP-IA CYCIDNE SEPARATOR A 302411-1 AUX 111ARY S IDLE N N/A 095 IN USE -

21 RWSP-IB CYCIDNE SEPARATOR B 302411-1 AUX 111ARY S IDLE N N/A 725 095 IN USE 101 7 RWV-150 RW RECIRCULATION FIDW 302411-1 AUXILIARY S CONTROL N CONTROLVALVE 095 CONTRE 21 SAHE-IA STATION AIRCOMPRESSOR 302-221-3 T1.1tBINE S OFF N N/A NONE 454 AFTER-COOLIR A 095 OFY 21 SAHE-IB STATION AIRECOMPRESSOR 302-221-3 RitBINE S OFF N N/A NONE 455 .

AfTERNR B 095 OFF 451 12 SAP-I A STATION AIR COMPRESSOR I A 302-221-3 RitBINE S OFF -N N/A NONE 095 OFF 452 12 SAP-IB STATION AIR COMPRESSOR IB 302-221-3 RitBINE S OFF N N/A NONE I

095 OFF 855 N/A SAV-5 AIR SUPPLY ISOLATION 302-271-2 TURBINE N OPEN N N/A I BETWEEN SA ANDIA 095 NED l

1 Appendix B 63 i

)  ;

w/ . x., a SEQ T CL 13NO EQUIP DESCRIPTION DRAWING BLDGI EVAL $$EL NOTE MOttM/ PM'R SUPORT DW INTERCONS EL DEtumm SCP-3 SECONDARY SERCIVES SC08. 302- TLitBINE S OFF Y MTMC-12 438 '5 13C C1DSED CYCIICOOLINO 228-3 095 ON BOOSTER PLMP 458 7 SCV M IAP-1 A &1AHLIACOOLING 302-221-3 TLitBINE S CONTROL N .N/A WATER CONTROLVALVE 108 CONTROL 459 7

• SCV-096 - IAP-1B & IAHLIB COOLING 302-211-3 TURBINE S CONTROL N N/A WATT.R CONTROL VALVE 108 CONTROL 457 8B SCV 099 IAP-I A & lAHLI A COOUNO IA01.302- TURBINE g CLOSED Y DPDP 3A ll WATER ISOIATION VALVE 211-3 107 OPEN 8B SCV-100 IAP-lB &lAHLIC COOUNG IA02,302- TURBINE S CIDSED Y DPDP-3B il 456 WATERISOIATION VALVE 211-3 107 OPEN N/A SCV-530 SC FROM SW DOIATION VAVII 302-211-3 TURBINE N CIDSED N N/A 870 107 OPEN SW FROM AIR COMPRESSORS 302-221-3 TURBINE N CLOSED N N/A 87i N/A SCV-534 ISOLATION VALVE 107 OPEN N/A SCV-535 SC TO AlR COkiPRESSORS 302-2Il-3 TURBINE N OPEN N N/A 85I ISOIATION VALVE 095 C1DSED .

N/A SCV-536 SC FROM AIR COMPRESSORS 302-211-3 TURBINE N OPEN N N/A 852 ISO 1ATION VALVE 095 CIDSED N/A SCV-537 SW FROM AIR COMPRESSORS 302-211-3 TURBINE N CIDSED N N/A 872 ISOLATION VALVE 108 OPEN ,

1g SF-9-FIT SPENT FUEL COOLANT FIDW 302 421-1 AUXIUARY S IN USE Y ACDP-515 193 TRANSMITTER I43 IN USE 21 SFDM-1 SPENT FUEL COOLANT 302 421-1 AUX 111ARY S IN USE N N/A 124 DEMINERALIZER I19 -

IN USE Appendix B 64 m

SEQ T. CL IDNO EQUlr DESCdIPTION DRA%ING BLDC/ EVAL . SEELNOTE NORW PWR SUPORT DW INTERCONS-R-

N EL . DESIRED 177 .21 SFHE-1A SPENT FUELCOOMR A 302 4 21-1 AUXIu'RY S IN USE N SW 119 IN USE 173 21 SFHE-1B SPENT FUELCOOLER B 302421-1 AUXRIARY S IN USE . N SW 119 IN USE 136 5 SFF-1A ' SPENT FUEL COOLANT PUMP A SF01,302- AUXILIARY S RUN Y MTMC4 IID 621-1 119 RUN 137 5 SFP-1B SPENT FUELCOOLANT PUMP B SF02. 302- AUXILIARY S RLH */ MDec-5 3D 621 1 119 RLH 766 13 SP-17-LT STEAM GENERATOR A LEVEL 302411-2 REACTOR S IN USE Y VBDP-8 095 IN USE 767 13 SP-Is-LT STEAM GENERATOR AIIVEL 302 4 11-2 REACTOR S IN USE Y VBDP-10 095 IN USE 768 18 SP-19-LT STEAM GENERATOR A LEVEL 302411-2 ' REACTOR S IN L4E Y \BDP-9 095 IN USE 769 1g SP-20-LT STEAM GENERATOR A LEVEL 3024Il-2 REACTOR S IN USE Y \BDP-11 095 IN USE SP-21-LT STEAM GENERATOR B LEVEL 302 4 11-2 REACIOR IN USE Y \BDP-s 770 18 S 095 IN USE 771 13 SP-22-LT STEAM GENERATOR B LEVEL 302-011-2 REACTOR S IN USE Y \BDP-10 095 IN USE 772 18 SP-23-LT STEAM GENERATOR B IIVEL 3024Il-2 REACTOR S IN USE Y VBDP-9 095 IN USE 773 Ig SP-24-LT STEAM GENERATOR B LEVEL 302 4 11-2 REACTOR S IN USE Y VBDP-ll '

095 IN USE 774 18 SP-25-LT STEAM GENERATOR A LEVEL 302 4 11-2 REACTOR S IN LGE Y \BDP-8 095 IN USE Appendix B 65

O v U see T CL ID NO EQUIP DESCRIFTION DRAWING BLDGf EVAL SSELNOTE NORM / PWR stPORT DW INTERCONS R

N EL DESIRED 775 1g SP-2RT STEAL! GENERATOR A LEVEL 3024II-2 REACTOR S IN USE - Y WDP-10 095 IN USE 776 1g sP-27-LT STEAM GENERATOR A LEVEL 302411-2 REACTOR S IN USE Y VBDP-9 095 IN USE 777. I8 SP-2s-LT STEAM GENERATOR A EVEL 3024Il-2 REACTOR g IN L5E Y VBDP-II 095 IN USE 773 13 sP-29-LT STEAM GENERATOR B EVEL 302 4 11-2 REACTOR g IN USE Y WDP-8 095 IN USE 779 1g SP-30-LT STEAM GENERATOR BIIVEL 302-011-2 REACTOR S IN USE Y VBDP-10 095 IN USE 780 13 SP-31-LT STEAM GENERATOR B LEVEL 302-011-2 REACTOR S IN USE Y VBDP-9 095 IN USE 781 Ig SP-32-LT STEAM GENERATOR B EVEL 302411-2 REACTOR S IN USE Y VBDP-II .

095 IN USE 440 5 SSP-4A CONDENSER A HOTWELL 302-181-1 TURBINE S OFT N N/A SAMPLE EXTRACTION PUMP 095 Of7 441 5 SSP-4B CONDENSER B HOTWELL 302-181-1 TURBINE S OFF N N/A SAMPI.IEXTRACTION PUMP 095 OFF 442 5 SSP-4C CONDENSER AB HOTWEll. 302-181-1 TURBINE S OFF N N/A-CROSSOVER SAMPLE 095 OFF EXTRACTION PUMP 443 5 SSP-4D LP HEATER SAMPLE 302-181-1 TURBINE S OFF N N/A EXTRACTION PUMP 095 OFF i 95 1g SW402-PT NUCLEAR SERVICE CCC PUMPS 302401-3 AUXIUARY S IN USE Y VBDP-1 1 OR DISCII/RGE PRESSURE 095 IN USE VBDP-5 II Appendix B 66

.n Q,

seq T CL- tono EQUIP DESCRIPTION ORAWING BUMM EVAL SSEL NOTE NORW FWIt SUPORT DW INTERCONS R

N . EL ymm 105 13 SW-135-PT NUCEAR SERVICE COOllNG NJ2401-3 AUXDlARY g N USE ,Y TPC WATER SURGE TANK PRESSURr 095 IN USE 107 13 SW-139 LT NUCEAR SERVICE COOtlNO 302401-3 AUXIUARY S N USE Y m WATER SURGE TANK EVEL 095 IN USE 302401-3 /lDGIJARY IN USE N 108 21

• SWHE-1A NUCLEAR SERVICE CCC HEAT EXCHANGER 3A s RWP-2AOR RWP-28 095 IN USE 21 SWHE IB NUCEAR SERVICE CCC HEAT 302401-3 AUXIUARY S IN USE N RWP-2A OR 109 EXCHANGER 3B 095 IN USE RWPM i

l10 21 Sw.tE IC NUCLEAR SERVICE CCC HEAT 302401-3 ALNIllARY S IN USE N. R%?-2AOR EXCHANGER 3C 095 IN USE RWP-2B 1II 21 SWHE-1D NUCLEAR SERVICE CCC HEAT 302401-3 AUXILLARY $ N USE N R%?-2A OR EXCHANGER 3D 095 IN USE RWP-2B 21 SWHE-2 SW SUPPLY TO PASS SAMPE 302401-4 AUXILIARY S OFF N N/A NONE 119 COOERS 302-756-1 108 OFF i

89 5 SWP-IA EMERGENCY NUCLEAR SWO2.M 302- AUXILLARY S OFF Y DPDP-5A lt SERVICE CCC PUMP 3A 601 3 095 ON AND MTSW-2C 97 5 SWP-IB EMERGENCY NUCEAR SWO3,302- AUXILLARY S OFF Y DPDP-5B 10 SERVICE CCC PUMP 3B 601-3 095 ON AND MTSW-2E 5 SWP-IC NORMALNUCLEAR SERVICE 302401-3 AUXILIARY S ON N N/A NONE 104 CLOSED CYCLE COOLING PUMP 095 OFF I 5 SWP-2A NUCEAR SERVICE BOOSTER 302401-1 AUXILLARY S ON N N/A NONE 57 PUMP A 8 095 W Appendix B 67

,m ,m

(%J ) (

w/

) (n

%/

sea T CL ID NO EQUlF DESCRIFTION DRAWING BLDG / EVAL SSEL NOTE NORM / FWR SUPORT DW INTERCONS R

N EL DESIRED 5 SWP-2B NUCIIAR SERVICE BOOSTER 30240I-1 AUXILLARY ON N N/A NONE 58 S PUMPB 095 OFF 106 21 SWT-1 NUCIIAR SERVICE CIDSED 302401-3 AUXILLARY S IN USE N N/A CYCLE SUROETANK 095 IN USE 174 7 ' SWV412 SEAL REWRN COOLERS 302401-4 AUX 1UARY S OPEN N IA SUPPLYISOLA110N VALVE I19 OPEN 165 21 SWV412- SWV-12 CONTROL 308-802 AUXIUARY S IN USE N N/A AR 119 IN USE 163 8B SWV-012 SWV-12 CovrROL SWO6 AUXIMARY S Y DPDP-SA 14 SVI gi, 164 8B SWV-012- SWV-12 CONTROL SWO6 AUXIUARY S Y DPDP-5B 15 SV2 gg9 47 7 SWV-035 INLETISOLATION FOR AHHL 3024011, AUXIUARY S OPEN Y DPDP-5421, 31A AND AHHL32A SW-06 095 OPEN IA 48 7 SWV-037 INIITISOIATION FOR AHHL 302401-1 AUXILIARY S OPEN Y DPDP-IB 6, 31B AND AllHL32B SW47 095 OPEN IA '

49 7 SWV439 INLETISOlATION FOR AHHL 302401-1, AUXIUARY S OPEN Y DPDP-3B 21, 31C AND AllHE-32C SW-07 095 OPEN IA 167 7 SWV-041 ISOLATION FROM OUTLETS OF 302401-1 AUXILIARY S OPEN Y DPDP-5A 21 AilllL31 A AND AllHL32A SW 08 119 OPEN IA 50 7 SWV-043 OUnITISOLATION FOR AlllIL 302401-1, AUX 1UARY S OPEN Y DPDP-lB 6, I 31B AND AHHL32B SW-08 095 OPEN IA 51 7 SWV-045 OurLETISOLATION FOR AllllL 302401-1, AUXILIARY S OPEN Y pppp.5B 21, 31C AND AllHE-32C SW-09 095 OPEN IA l

I Appendix B 68 e__ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ __

n.

(,x\

.NJ d' (m)

V-seq T CL DNO . EQUIP DESCRIFTION - DRAWING . BLDGf EVAL SSEL MOTE NORW PH1L SUFORT DW INTERCONS A

EL nessman

'N 52 7 SWV447 ISOLATION TO MUHE-lB AND 302401-1 AUX 111ARY $ OPEN Y DPDP-5A 14 WDHE1 SW-10 - 095 OPEN OR DPDP-5B 15,lA 53 7 - SWV448 LE1DOWN COOER 3BINLET 302401-1 AUXILLARY $ OPEN Y . DPDP-5A I5 ISOIA110N VALVE SW-11 095 OPEN OR DPDP-5B 14 IA 54 7 SWV-049 LETDOWN COOER 3B 302401-1 AUXIUARY S OPEN Y DPDP-5A 15 DISCHARGEISOLATION VALVE SW-13 095 OPEN M DPM-5B 14,IA 55 7 SWV450 OtnHTISOIATION FOR MUHE- 302401-1 AUXIUARY S OPEN Y pror-5A I4 I A AND WDHE-1 SW-12 095 OPEN OR DPDP-5B 15,IA N/A SWV-103 SC FROkt SWISOIATION VALVE 302401-4 INTER N CIDSED N N/A 842 095 OPEN SW TO SCISOLATION 302401-4 INTER N CIDSED N N/A 843 N/A SWV-104 095 OPEN 7 SWV-151 IC FROh! RB FAN COOLERS SW29,302- AUX 111ARY S OPEN N SW-151-SV 118 ISOLATION VALVE 601-1 100 CIDSED 21 SWV-15 l- AIR RESERVOIR FOR SWV-151 308-802 AUXILLARY S N USE N N/A 116 AR 100 ' IN USE 8B SWV-151-SV SWV-ISI CONTROL SW29 AUXILIARY S Y DPDP-5A 16 '

80 095 7 SWV-152 IC TO RB RAN COOLERS 302401-1 AUXIUARY S OPEN N S%T-152-117 ISOLATION VALVE 100 CIDSED SVIOR SWV-152 SV2 SWV-152- AIR RESERVOIR FOR SWV-152 308-802 AUXIUARY S IN USE N N/A

, 115 21 I AR 100 IN USE 1

1 Appendix B 69.

~

SEQ T CL ID NO EQUlF DESCRIPTION DRA%TNG BLDG / EVAL ' SSELNOTE ' NORM / FWR SUFORTDW INTERCONS R

N EL DESIRED 81 88 SWV-152 SWV-152 CONTROL SW30 AUXILLARY S Y SPSP-3A 16 SVI 095 82 8B SWV-152- SWV-152 CONTROL SW30 AUXILLARY S Y DPDP-5B 17 SV2 095 92 7

• SWV-353 SW TO RB FAN COOLERS ISOLATION VALVE 302401-1 AUXIUARY S CLOSED N SWV-353 SVIOR 095 OPEN 5%T-353-SV2 96 2[ SWV 353- AIR RESERVOIR FOR SWV-353 308-802 AUXIUARY S IN USE N N/A .

AR 095 IN USE 93 SB SWV-353- SWV-353 CONTROL SW24 AUXIUARY S Y DPDP-5A 17 SVI 095 83 8B SWV-353- SWV-353 CONTROL SW24 AUXILIARY S Y ~ DPDP-IB6 SV2 095 78 7 SWV-354 SW FROh! RB FAN COOLERS 302-601 1 AUXIUARY S CLOSED N SwT-354-ISOLATION VALVE 095 OPEN SV1OR SWV-354-SV2 87 21 SWV-354- AIR RESERVOIR FOR SWV 354 308-802 AUXIUARY S IN USE N N/A AR 095 IN USE 84 8B SWv.354- SWV-354 CONTROL SW25 AUXIUARY S Y DPDP-5A 17 SVI 095 85 8B SWV-354- SWV 354 CONTROL SW25 AUXIUARY S Y DPDP-IB 6 SV2 995 79 7 SWV-355 IC FROkt RB FAN COOLERS 302 4 01-1 AUXILIARY S OPEN N S%T-355-SV ISOLATION VALVE 095 CIDSED Appendix B 70 a - ._ _ __ _ - _ _ _ _ _ _ _ . - _ - _ _ - - -_- _ _ __ _ - - - - - - - - . - _ - _ _ - - - - - - - --

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t I l

%)  % _J SEQ T CL' IDNO EQUIP DESCRIFTION DRA%1No BLDGf EVAL SSEL NOTE. NORM / F%R SUFORT DW INTERCDM5 R

N EL DESERED 88 21 SWV-355- AIR RESERVOIR FOR SWV-355 308-802 AUXILLARY S IN USE N N/A' AR 095 IN USE 86 3B SWV-355-SV SWV-355 CONTROL SW26 AUXILJARY S Y DPDP-5B 16 095 607 20 TPC TitANSMITTER POWER SUPPLY CONTROL $ N/A N

. CABINETS A & B 124 N/A 686 14 VBDP41 REOUIATEDINSTRUMENT BUS 206-041 CONTROL S IN USE Y VBTR-IA 3A 145 IN USE 687 14 VBDP42 REGULATED INSTRUMENT BUS 206441 CONTROL S IN USE Y VBTR-1B 3B 145 IN USE 6gg 14 VBDP-03 \TTAL BUS A 206-017 CONTROL S IN USE Y VBXS-IA 145 IN USE 689 14 VBDP-04 \TFAL BUS B 206 4 17 CONTROL 5 IN USE Y VBXS-la 145 IN USE 690 14 VBDP-05 VITAL BUS C 206-017 CON 11tOL S IN USE Y VBXS-IC 145 IN USE 691 20 VBDP 120 VOLT VITAL BUS 3C CONTROL S SIP STAlVS INDICATION PANEL 145 692 14 VBDP46 VITAL BUS D 206417 CONTROL S IN USE Y \BXS-ID 145 IN USE 693 20 VBDP46- 120 VOLT \TTAL BUS 3D CONTROL S SIP STATUS INDICATION PANEL g43 694 14 VBDP-07 CohlPtTFER l20 VAC 206-041 CONTROL S IN USE Y \BXS-lE DISTRIBUTION PANEL I45 IN USE 612 14 VBDP-08 EFIC \TTAL BUS A 206-017 CONTROL S IN USE Y VBXS-3A 124 IN USE Appendix B 71 l

_ _ - - - - - , - - - - - -___----__------w - - - - - - - - - - - - - - - - - - - - - - - - -------s-- - " - - - - - - - ^ - - - - - ----------------------------'-------i

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.h,m, (_) .O sEn T CL ID NO EQUlf DESCRIFTION . DRAWINC . BLDG / EVAL' SSELNOTE NORW PH1t SUPORT DW ' INTERO0NES R

.N EL DESERED l,

~613 20 VBDP- \TTAL BUS STATUS CNTROL S 08/12/13-SIP INDICATION PANEL A FOR 124 VBDP-5/12/13 VBDPM EFIC VITAL BUS C 206 017 CONTROL. S IN USE Y VBX53C 614 14 124 IN USE 615 20 .VBDP&- VITAL BUS STATUS CWTROL 5 SIP INDICATION PANELC FOR 334 VBDP-9 608 -14 VBDP-10 EFIC \TTAL BUS B 206417 CONTROL 3 IN USE Y VBX53B 124 IN USE 609 20 VBDP- %TTAL BL5 STATUS CONTROL S 10/14/15-SIP INDICATION PANEL B FOR 124 VBDP-10/14/I5 610 14 VBDP-lI EFIC VTTAL BUS D 206 417 CONTROL 5 IN USE Y VBXS-3D 124 IN USE 611 20 VBDP-lI- %TTAL BUS STATUS CONTROL 5 SIP INDICATION PANEL D FOR 124 VBDP-11 517 14 VBDP-12 120 VOLT REGUIATED CONTROL S DISTRIBUTION Ps.NEL 108 518 14 VBDP-13 120 VOLT REGUIATED CONTROL S DISTRIBUTION PANEL gog 519 14 VBDP-14 120 VOLT REGULATED CONTROL S DISTRIBLRION PANEL los 520 14 VBDP-I5 120 VOLT REGULATED CONTROL S DISTRIBUTION PANEL .gog Appendix B 72

N. .

SEQ T CL ID NO EQUIF DESCRIFTION DRAWLW BLDCI EVAL SSEL NOTE NORM / P%R SUFORY DW INTERCONS R

N EL DESIRED 201 16 ' VBIT-IA DUALINIUTINVERTER 3A 206417 .COhTROL 5 IN USE Y MTMC-3 108. IN USE 3AL* '

DPDP-1A4 N USE~ Y MTMC4 i 207 16 VBir-1B DUALINPUTINVERTER3B 206-017 CONTROL 5 108 IN USE 4ALOR DPDP-1B 15 208 16 VBIT-lC DUALINPUTINVERTER3C 206417 Coh*IltOL S IN USE Y MTMC-3 i-los IN USE 2ALOR DPDP-1 A 5 209 16 VBir-ID DUALINPUTINVERTER 3D 206-017 CONTROL S IN USE Y MDeC4 108 IN USE 4AR M DPDP-1B 16 210 16 VBIT-lE DUALINPUTINVERTER 3E 206416 CO!(FROL S IN USE Y MTMC18 108 IN USE OR DPDP-IC 616 4 VBTR-IA CONSTANT VOLTAGE 206 441 COVFROL S IN USE Y. MTMC-1 TRANSFORMER A 124 IN USE 4 VBTR-1B CONSTANT VOLTAGE 206441 CONTROL S IN USE Y MTMC-2 617 TRANSFORMER B 124 IN USE 521 4 VBTR-2E 480/120V REDUNDANT POWER 206416 CONTROL S IN USE Y MTMC-18 SUPPLY TRANSFORMER 3E 10s IN USE 522 4 VBTR-3E REDUNDANT POWER SUPPLY 206416 CONTROL S IN USE Y VBTR-2E SOIATRON 3E 108 IN USE

-618 4 VBTR-4A REGULATmO TRANSFORMER A 206 4 17 CONTROL S STANDBY Y MTMC-4 5BL 124 STANDBY 619 4 VBTR-4B REGULATING TRANSFORMER B 206417 CONTROL S STANDBY Y MTMC-5 3BL 124 STANDBY Appendix B 73

f .

%s  % %s -

SEQ T CL ID NO EQUIP DESCRIPTION DRA%1NG BLDG EVAL SSEL NOTE NORMt FWR SUFOstT DW INTEDCOPts R

N EL DESIRED i 620 4 VBTRAC REGULATNG TRANSFORMER C 206417 CONTROL S STANDBY Y- MTMC4 SBR '

124 STANDBY 621 4 M 4D REGULATmo TRANSMRMER D 2064 17 CONTROL S STANDBY Y, MTMC-5 3BR 124 STANDBY 523 2 \ M IA \TTAL BUS TRANSFER S%TTCH 206417 CONTROL 3 IN USE Y VBIT-IAOR A 108 IN USE N-4A 524 2 VBXS-1B \TTAL BUS TRANSFER S%TTCH 206417 CONTROL S IN USE Y . VBIT-lB OR B 108 IN USE M4 525 2 VBXS-IC VTTAL BUS TRANSFER SWITCH 206417 CONTROL S IN USE Y VBIT-IC OR [

C 108 IN USE M-4C 526 2 VBXS-1D VITAL BUS TRANSFER SWTTCH 206417 CONTROL 5 IN USE Y VBIT-1D OR D 108 IN USE M-4D 527 2 VBXS-1E MANUALTRANSFER 5%TTCH 206415 CONTROL S IN USE Y VBTR-3E OR 108 IN USE VBfT-lE 695 20 VBXS-2A AUTO TRANSFER S%TICH FOR 209-058 VB- CONTROL S IN USE Y VBDP-I II NNI 08 145 IN USE OR VBDP-5 7 696 20 \ M 2B AUTO TRANSFER SWITCH FOR 209458 VB- CONTROL S IN USE Y VBDP-2 4 OR ICS 08 145 D4USE VBDP-4 23 528 2 VBXS-3A Ef1C VITAL BUS TRANSFER 206-017 CONTROL S IN USE Y VBfT-I A OR 5%TTCH A 108 IN USE VBTR-4A 2 VBXS-3B EFIC VITAL BUS TRANSFER 206-017 CONTROL IN USE Y VBfT-1B OR 529 S SWTTCH B 108 IN USE VBTR-4B 2 VBXS-3C EFIC VITAL BUS TRANSFER 206-017 CONTRO! S IN USE Y VBIT-IC OR 530 SWITCll C 108 IN USE VBTR E Appendix B 74

p Q . /~')

k_) b/-

sEn T- CL In No EQUIF DESCRIPTION DRAWING BLDCI EVAL . SSELNOTE NORM / ' FWR - SUFORT DW INTERCONS 3 EL nruman 531 2 N3D EE VITAL BW TRANSFER - 206417 CONTROL 3 E USE Y VBrT-ID OR SWITCH D 108 IN USE N4 782 21 %NI REACTOR COOLANT DRAIN 3024 01-1 REACTOR S IN USE N SW TANK N 095 IN USE 16 12 , WDF-1A WASTEGASCOMPRESSOR A 302401-4 AUXILIARY S OFF N N/A NONE 095 OFF 17 12 WDF-1B WASTE GAS CX&lFRESSOR B 3024 01-4 AUXILLARY g OFF N N/A NONE 095 OFF 883 21 WDT-IA WASTEGAS DECAY TANK IA M4I22 Rev.4 AUXHJARY 095 gg4 21 WDT-IB WASTE GAS DECAY TANK iB M4122 Rev. 4 AUXILIARY 095 885 21 WDT-lC WASTE GAS DECAYTANK IC M4122 Rev 4 AUXILLARY 095 18 21 WDT-3A RC BLEED TANK 3A 302 4 81-4 AUXHJARY S IN USE N N/A 095 IN USE 46 2I WDT-3B RC BLEED TANK 3B 302441-4 AUXILLARY S IN USE N N/A 095 IN USE 21 WDT-3C RC BLEED TANK 3C 302481-4 AUXILIARY IN USE N N/A 59 S 095 IN L4E 783 2I WDT-5 REACTOR COOLANT DRAIN 302491-3 REACTOR S IN USE N N/A TANK 095 IN USE Appendix B 75 O

C

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!O i

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ese l J

i FLORIDA POWER CORPORATION '

l CRYSTAL RIVER UNIT 3 lo i

! APPENDIX C l

1 i

l SCREENING VERIFICATION DATA SHEETS l .

(SVDS) l l 1 iO i  ;

,~

(d APPENDIX C: Screening Verification Data Sheets (SVDS)

December 15,1995 CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 14 ACDP-05 DIESEL ROOM 480 VOLT DIESEL 119 119 Y Y Y Y Y DISTRIBUTION PANEL 3A

~

14 ACDP-06 DIESEL ROOM 480 VOLT DIESEL 119 119 Y Y Y Y Y DISIRIBUTION PANEL 3B 14 ACDP-51 CONTROL COMPLEX CONTROL 145 302/H 095 Y Y Y Y Y DIS ~IRIBUTIONPANEL A 4 ACDP-51-T CONTROL COMPLEX CONIROL 124 302/H 095 Y Y Y Y Y DISTRIBlJTION PANEL A TRANSFORMER 14 ACDP-52 CONTROL COMPLEX CONTROL 145 302/H 095 Y Y Y Y Y DISTRIBUTION PANEL B 4 ACDP-52-T CONTROL COMPLEX CONIROL 124 302/H 095 Y Y Y Y Y DISTRIBUTION PANEL B TRANSFORMER 14 ACDP-68 ES DISTRIBUTION PANEL 3AB CONTROL 124 303/G 095 Y Y Y Y Y 4 ACDP-68-T ES DISTRIBUTION PANEL CONTROL 124 303/G 095 Y N Y Y~ N 3AB TRANSFORMER 8B AH-033-ASV AHD-1, AHD-ID, AHD-2, & CONTROL 164 302/H 095 Y Y N/A Y Y' AHD-3 CONTROL 8B AH-033-SV AHD-1, AHD-1D, AHD-2, & CONTROL 164 302/H 095 Y Y N/A Y Y AHD-3 CONTROL 8B AH-194-SV AHD-13 & AHD-14 CONTROL CONTROL 164 303/G 095 Y Y N/A Y Y 8B AH-195-SV AHD-15 & AHD-16 COMTROL CONIROL 164 303/G 095 Y Y N/A Y Y 10 AH-l%-POSI AHD-1 CONTROL CONIROL 160 301/1 _ 095 N N Y Y N Appendix C 1 n __ _ _ _ _ _ _ _ . - _ _ - _ _ _ _ _ _ _ _ _- . . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - __- .__

.. . - . . ~- - --

,/ 3 m .(-

l Gl l CLASS ID NO EQUIF DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH' INTER EQUIP L RC EL OK OK OK OK OK 10 AH-l%POS2 AHD-2 CONIROL CONIROL 108 303/G 095 Y N Y Y N 10 AH-l%POS3 AHD-3 CONTROL CONIROL 164 302/H 095 Y N Y Y N

, 10 AH-l%POS4 AHD-ID CONIROL AUXILIARY 160 307/H 095 Y Y Y Y Y i

8B AH-1%SV AHD-1, AHD-1D, AHD-2, & CONIROL 164 302/H 095 Y Y N/A Y Y AHD-3 CONIROL 8B AH-199-SV AHD-4 & AHD-5 CONTROL - CONTROL 164 302/H 095 Y Y N/A Y Y 8B AH-200-SV AHD4 & AHD-7 CONTROL CONTROL 164 303/H 095 Y Y N/A Y Y 8B AH-246-SV AHD-12 CONTROL CONIROL 164 302/H 095 Y Y N/A Y Y 8B AH-250-SV AHD-17 & AHD-22 POST- AUXILIARY I19 303/1 095 Y Y N/A Y Y ACCIDENT CONTROL 8B AH-310-SV AHD-87 CONTROL AUXILIARY I19 304/1 095 Y Y N/A Y Y 8B AH-311-SV AHD-88 CONIROL . AUXILIARY 119 304/1 095 Y Y N/A Y .Y 8B AH-355-'SV AHD43 CONTROL DIESEL i19 HVAC CAB 20 119 Y Y- N/A Y Y 8B AH-356-SV AHD43 CONIROL DIESEL 119 HVAC CAB 20 119 Y Y N/A Y Y 8B AH-357-SV AHD41 CONTROL DIESEL 119 HVAC CAB 20 119 Y Y N/A Y Y 8B AH-358-SV AHD-62 CONTROL DIESEL 119 HVAC CAB 20 119 Y Y N/A Y Y 88 AH-365-SV AHD40 CONIROL DIESEL 119 HVAC CAB 19 119 Y Y N/A Y Y 8B AH-366-SV AHD40 CONTROL DIESEL 119 HVAC CAB 19 119 Y Y N/A Y Y 8B AH-367-SV AHD-58 CONTROL DIESEL 119 HVAC CAB 19 119 Y Y N/A Y Y 8B AH-368-SV AHD-59 CONTROL DIESEL 119 HVAC CAB 19 119 Y Y i"A Y Y 8B AH-381-ASV AHD-1, AHD-ID, AHD-2, & CONTROL 164 302/H 095 Y Y N/A Y Y AHD-3 CONTROL ,

Appendix C 2

,c .

C k h,,

- CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE ' CAF CAV ANCH LMIER EQUIP L RC EL OK OK OK OK OK 8B AH-381-SV AHD-1, AHD-ID, AHD-2,& CONIROL 164 302/H 095 Y Y N/A Y Y AHD-3 CONIROL 12 AH-506-PS AHP-1A A AHP-1B CONTROL CONTROL 164 303/F 095 Y Y Y' Y Y 12 AH-508-PS AHP-IC & AHP-ID CONTROL CONTROL 164 303/F 095 Y Y Y Y Y 8B AH-517-SV - CONIROL 164 303/F 095 Y Y N/A Y Y 8B AH-518-SV CONTROL 164 303/F 095 Y Y N/A Y' Y 8B AH-648-ASV AHD-1, AHD-ID, AHD-2, & CONTROL 164 302/H 095 Y Y N/A Y Y AHD-3 CONTROL 8B AH-648-SV AHD-1, AHD-ID, AHD-2, & CONIROL 164 302/H 095 Y Y N/A Y Y AHD-3 CONIROL 8B AH-649-ASV AHD-1, AHD-ID, AHD-2, A CONIROL 164 302/H 095 Y Y N/A Y Y AHD-3 CONTROL 8B AH-953-SV AHD-99 CONTROL CONIROL 164 HVAC CAB 095 Y Y N/A Y Y 9AB 8B AH-966-SV AHD-1 CONIROL CONIROL 164 302/1 095 Y Y N/A Y Y 8B AH-%7-SV AHD-1 & AHD-ID CONTROL AUXILIARY 160 302/1 095 N Y N/A Y N 8B AH-%8-SV AHD-2 CONTROL CONTROL 164 303/H 095 Y Y N/A Y- Y 8B AH-%9-SV AHD-3 CONTROL CONTROL 164 302/H 095 Y Y N/A Y Y 8B AH-970-SV AHD-99 CONTROL CONIROL 164 303/H 095 Y Y N/A Y Y 8B AH-971-SV AHD-12 CONTROL CONIROL 108 304/G 095 Y Y N/A Y Y 20 AHCP-4 SCR CABINET FOR AIDE-4A CONIROL 164 302/G 095 Y Y Y Y Y AND AHIE-4B 10 AHD-01 CONTROL COMPLEX MAKE. CONTROL 164 301/1 095 Y Y Y Y Y UP AIR Appendix C 3

f' -

l  % O U i

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 10 AHD41D CONTROL COMPLEX MAKE- AUXILIARY 160 307M 095 N. Y Y Y N UP AIR 10 AHD-02 PNEUMATIC RELIEF TO CON 2OL 164 302M 095 Y Y Y Y- _Y AD40 SPHERE 10 AHD-03 CONTROL COMPLEX FANS CONIROL 164 302-H 095 Y Y Y Y Y INTAKE 10 AHD-04 AHF-17A INTAKE CONIROL 164 302M 095 Y Y Y Y Y 10 AHD-05 AHF-17A DISCHARGE CONIROL 164 304/H 095 Y Y Y Y Y 10 AHD-06 AHF-17B INTAKE CONIROL 164 303/H 095 Y Y Y Y Y 10 AHD-07 AHF-17B DISCHARGE CONTROL 170 302/H 095 Y Y Y Y Y  ;

10 AHD-12 SUPPLY TO CHEMLAB CONTROL 108 303/G 095 Y Y Y Y Y 10 AHD-13 AHF-19A INTAKE CONIROL 164 302/G 095 Y Y Y Y Y 10 AHD-14 AHF-19A DISCHARGE CONIROL 164 302/H 095 Y Y Y Y Y 10 AHD-15 AHF-19B INTAKE CONIROL 164 302/G 095 Y Y Y Y Y-10 AHD-16 AHF-19B DISCHARGE CONTROL 164 302/H 095 Y Y Y Y Y 10 AHD-17 95* ELEVATION RETURN CONTROL 103 303/H 095 Y Y Y Y Y 10 AHD-22 SECONTARY PLANT LAB CONTROL 104 303/F 095 Y Y Y Y Y HOOD SUPPLY 10 AHD-58 AHF-22C DISCHARGE DIESEL 124 300B/Q 119 Y Y Y Y Y 10 AHD-59 AHF-22D DISCHARGE DESEL 120 300B/Q 119 Y Y Y Y Y 10 AHD-60 EGDG-1B INTER-ROOM DESEL 124 300B/P 119 Y Y Y Y Y 10 AHD-61 AHF-22A DISCHARGE DIESEL 124 300A/P 119 Y Y Y Y Y-Y Y Y 10 AHD-62 AHF-22B DISCHARGE DESEL 124 300A/P '-

119 Y Y_

Appendix C 4 m ---- _ -_ --_ ____--_ ---- ---_-------_

(- .

V b b. -_

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 10 AHD-63 EGDG-IA DGER-ROOM DIESEL 124 300A/P 119 Y Y Y Y Y 10 AHD-87 AHF-8A DISCHARGE AUXILIARY 128 303/J 095 Y Y Y Y Y 10 AHD-88 AHF-8B DISCHARGE AUXILIARY 124 303/J 095 Y Y Y Y Y 10 AHD-99 VENTILLATION EQUIPMENT CONIROL 164 303/H 095 Y Y Y Y Y ROOM SUPPLY AIR 21 AHDR-1A CONTROL COMPLEX HVAC CONIROL 164 303/F 095 Y Y N/A N/A Y COMPRESSED AIRDRYER A 21 AHDR-1B CONIROL COMPLEX HVAC CONIROL 164 303/F 095 Y Y N/A N/A Y COMPRESSED AIRDRYERB 9 AHF-01 A REACTORBUILDING AIR REACTOR 126 319/RB 095 Y Y Y Y Y HANDLING FAN A 9 AHF-01B REACTORBUILDING AIR REACTOR 103 319/RB 095 Y Y Y Y Y HANDLING FAN B 9 AHF-01C REACTORBUILDING AIR REACTOR 103 323/RB 095 Y Y Y Y Y HANDLING FAN C 10 AHF-08A SPENT FUEL COOLANT PUMP AUXILIARY I19 304/J 095 Y Y Y Y Y A AIR HANDLING 10 AHF-088 SPENT FUEL COOLANT PUMP AUXILIARY I19 304/J 095 Y Y Y Y Y B AIRliANDLING 9 AHF-17A CONTROL COMPLEX CONTROL 164 302/H 095 Y N N U N~

NORMAL SUPPLY FAN A 9 AHF-17B CONTROL COMPLEX CONTROL 164 302A/H 095 Y N N U N NORMAL SUPPLY FAN B ,

9 AHF-19A CONTROL COMPLEX CONTROL 164 302/H 095 Y Y Y Y Y ,

RETURN FAN A 9 AHF-19B CONTROL COMPLEX CONTROL 164 302A/H 095 Y Y Y Y Y RETL'RN FAN B Appendix C 5 i

m_____________.______ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM -BASE CAF ICAV ANCH INTER ' EQUIP L RC EL OK OK OK OK OK 9 AHF-22A DIESEL GENERATOR ROOM DIESEL 137 i!9 Y Y Y Y Y A SUPPLY

9. AHF-22B DIESEL GENERATOR ROOM DIESEL 131 119 Y Y Y .Y Y A SUPPLY 9 AHF-22C DIESELGENERATORROOMB DIESEL 137  !!9 Y Y Y Y Y

~

SUPPLY 9 AHF-22D DIESEL GENERATOR ROOM B DIESEL 131 119 Y Y Y Y Y SUPPLY 10 AHF-54A EFIC ROOMS COOLING A CONTROL 124 EFIC ROOM A 095 Y- Y Y Y .Y 10 AHF-54B EFIC ROOMS COOLING B CONTROL 124 EFIC ROOM B 095 Y Y Y Y Y 10 AHHE-04A HEATING UNIT A FOR CONTROL 170 302/G 095 Y Y Y- Y Y CONTROL COMPLEX 10 AHHE-04B HEATING UNIT B FOR CONIROL 170 .302A/G 095 Y Y. .Y Y Y-CONTROL COMPLEX 10 AHHE-05A COOLING UNIT A FOR CONTROL 170 302/F 095 Y Y Y Y Y CONTROL COMPLEX ,

10 AIDIE-OSB COOLING UNIT B FOR CONTROL 170 302A/F 095 Y Y Y Y Y CONIROL COMPLEX 21 AHHE-13A COOLING COILS FOR INTER 095 305/G 119 Y Y N/A N/A Y REACTOR BUILDING PENETRATIONS A 21 AHHE-13B COOLING COILS FOR INIER 095 305/G 119 Y Y N/A N/A Y REACTOR BUIDLING .

PENETRATION B 10 AHHE-29A COOLING UNIT FOR SFP-1 A AUXILIARY l19 304/J 095 Y .Y Y Y Y l

10 AHHE-29B COOLING UNIT FOR SFP-1B AUXILIARY I19 304/J 095 Y Y Y Y Y 21 AHHE-30A COOLING UNIT FOR DCP-1 A AUXILIARY 095 306/T 095 Y Y N/A N/A Y Appendix C 6

. ,y O V b,,

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 21 AHHE-30B COOLING UNIT FOR DCP-1B AUXILLARY 095 306/T 095 Y Y N/A N/A Y 10 AHHE-31 A COOLING UNIT A FOR REACTOR 126 RB-319, AHF- 095 Y Y Y Y Y REACIORBUILDING 1A 10 AHHE-31B COOLING UNIT B FOR REACTOR 126 RB-319, AHF- 095 Y Y Y Y Y REACTOR BUILDING IB 10 AHHE-31C COOLING UNIT C FOR REACTOR 103 RB-323, AHF- 095 Y Y Y Y Y REACIOR BUILDING 1C 10 AHHE-32A MOTORCOOLERFOR AHF-1A REACTOR 126 RB-323, AHF- 095 Y Y Y Y Y lA 10 AHHE-32B MOTOR COOLER FOR AHF-1B REACTOR 103 RB-319, AHF- 095 Y Y Y Y Y IB 10 AHHE-32C MOTOR COOLER FOR AHF-IC REACTOR 103 RB-319, AHF- 095 Y Y Y Y Y IC 10 AHHE-43 COOLING UNIT A FOR EFIC CONTROL 124 EFIC ROOM 095 Y Y Y Y Y ROOMS 10 AHHE-44 COOLING UNIT B FOR EFIC CON 1ROL 124 EFIC ROOM 095 Y Y Y Y Y ROOMS 12 AHP-01 A CONTROL COMPLEX HVAC CONTROL 164 EQUIP ROOM- 095 Y N N Y N AIR COMPRESSOR A 12 AHP-OlB CONTROL COMPLEX HVAC CONTROL 164 EQUIP ROOM 095 Y N N Y N AIR COMPRESSOR B 12 AHP-01C CONTROL COMPLEX HVAC CONIROL 164 EQUIP ROOM 095 Y N N Y N AIR COMPRESSOR 12 AHP41D CONTROL COMPLEX HVAC CONTROL 164 EQUIP ROOM 095 Y N N Y N AIR COMPRESSOR D 20 AHPL-1 PANEL CONTROL 164 302/11 095 Y Y Y Y Y.

TURBINE I19 Y Y N/A Y 8A ARV-48 VACUUM BREAKER RELIEF -

095 Y-FOR CDHE-4A Appendix C -7

=_ ___ - . _ _ _ _ . _ _ - - _ _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ _

,.- ,,~, ,,

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK .OK OK OK OK 8A ARV-49 VACUUM BREAKER RELIEF TURBINE 127 308/E 095 Y Y N/A Y Y FOR CDIE-4B SA ASV-005 EFIB-1 STEAM ADMISSION INTER 095 308/H 119 Y Y N/A Y Y 0 ASV-050 EFIB-1"IRIP &111ROTTLE INTER 095 308/H 119 Y Y N/A Y Y 8A ASV-204 EFIB-1 STEAM ADMISSION INIT_R 095 308/H I19 Y Y- N/A Y Y 20 ATCP-1 ANTICIPATED TRANSENT CONIROL 124 EFIC ROOM C 095 Y Y Y N N W11110UT SCRAM LOGIC CABINET 5 BSP-IA REACTOR BUILDING SPRAY AUXILIARY 075 305/N 095 Y Y Y Y Y PUMP A 5 BSP-1B REACTOR BUILDING SPRAY AUXILIARY 075 305/N 095 Y Y Y Y Y PUMP B 19 CA-10-TE BOTTOM BORIC ACID AUXILIARY 119 302/O 095 Y Y N/A Y Y STORAGE TANK CAT-5A 18 CA-11-LT BORIC ACID STORAGETANK AUXILIARY I19 302/O 095 Y Y Y Y Y A

19 CA-12-TE BOTTOM BORIC ACIT AUXILIARY 119 302/O 095 Y -Y N/A Y Y STORAGE TANK CAT-5B i

18 CA-13-LT BORIC ACID STORAGE TANK AUXILIARY 119 302/O 095 Y Y Y Y Y B

21 CAHE-1 PRESSURIZER SAMPLE AUXILIARY 095 304/H 095 Y Y N/A N/A Y l COOLER

! 21 CAHE-2A STEAM GENERA 1DR A AUXILIARY 095 304/H 095 Y Y N/A N/A Y l SAMPLE COOLER l 21 CAHE-2B STEAM GENERATOR B AUXILIARY 095 304/H 095 Y Y N/A N/A Y SAMPLE COOLER l

i 2i CAFE-5 PASS RC SAMPLE COOLER INTER 095 -

119 Y Y N/A N/A Y l

Appendix C 8 N _ - - - _ _ -_ __ ___ _ _ _ . , _ _ _-. . . - - . _ _ - - _ _ _ _ - _ - _ _ . - - _ _ _ _ - - - _

CLASS -ID MO EQUIP DESCRIPTION BLDG- E ROOM BASE . CAF CAV ANCH INTER EQUIP-L RC EL OK- OK OK OK OK 21 CAHE-6 PASS DECAY HEAT SAMPLE AUXILIARY 095 095 Y Y N/A N/A Y-COOLER 21 CAHE-8 PASS RC SAMPLE PRE- INER 095 119 'Y- Y N/A N/A Y COOLER

-5 CAP-IA BORIC ACID PUMP A AUXILIARY I19 302/O 095 Y Y Y. Y YL 5 CAP-1B BORIC ACID PUMP B AUXILIARY 119 302/O 095 Y N N Y N 21 CAT-5A BORIC ACID STORAGE A AUXILIARY I19 302/O 095 Y Y N/A N/A Y 21- CAT-5B - BORIC ACID STORAGE-TANK AUXILIARY l19 303/O 095 Y Y N/A N/A' Y B

8B - CAV-002 PZR AND LETDOWN DUER 095 305/H I19 Y Y N/A Y Y OIRSIDE PENETRATION SAMPLE ISOLATION 7 CAV-057 BORIC ACID PUMP TO MAKE- AUXILIARY 119 304/M 095 Y Y N/A Y Y UP TANK 8B CAV-057-SV CAV-57 CONTROL AUX 1LIARY 119 . 304/M 095 Y Y N/A Y Y 7 CAV-060 BORIC ACID PUMP TO MAKE- AUXILIARY 121 304/M 095 Y Y N/A Y Y UP TANK 8B CAV-060-SV CAV-60 CONTROL AUXILIARY l19 304/M 095 -Y Y N/A Y Y 8A CAV-126 RC LETDOWN SAMPLE REACTOR 095 305/K 095 Y ,

INSIDE PENETRATION ISOLATION VALVE 20 CCBT CENTRAL CONTROL BOARD CONTROL 145 302/H 095 'Y Y Y Y Y  :

TERMINATION CABINET 18 CD-067-LT1 CONDENSATE STORAGE TURBINE I19 311/C 095 Y Y .Y Y Y TANK LEVEL 18 CD-100-LT CONDENSER CDIE-4A TURBINE 095 306A/Cl ^-. 095 Y Y Y Y Y -

HOTWELL LEVEL

• Appendix C 9

~

U N N CLASS ID NO EQUIF DESCRIFTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK- OK OK OK 18 CD-101-LT CONDENSER CDHE-4B WRBINE 095 306A/E 095 Y Y Y Y Y HOTWELL LEVEL 21 CDHE-4A MAIN CONDENSER A TURBINE 095 306/D 095 Y Y N Y N

• 21 CDHE-4B MAIN CONDENSER B TURBINE 095 307/D 095 Y Y N Y N 6 CDP-1A CONDENSATE PUMP A TURBINE 095 305/B2 095 Y Y Y Y Y 6 CDP-1B CONDENSAT1! PUMP B TURBINE 095 308/B2 095 Y Y Y Y Y 21 CDT-1 CONDENSATE STORAGE WESTBERM 119 311/D 119 Y Y N/A N/A Y TANK 0 CEILING CONIROL ROOM CEILING CONIROL 145 301-303/F-1 095 Y N/A N N N 8A CFV-5 CORE FLOOD TANK A REACTOR 119 308/J 095 Y Y N/A Y Y DISCHARGE ISOLATION 8A CFV-6 CORE FLOOD TANK B REACTOR I19 305/L -095 Y Y N/A Y Y DISCHARGE ISOLATION 18 CH-378-LYT CHV-68 CONTROL OF CHHE- CONTROL 164 301/F 095 Y Y Y Y Y IA 18 CH-379-PT CHV-69 CONTROL OF CHHE- CONIROL 164 301/G 095 Y Y Y Y Y IB 11 CHHE-IA CONTROL COMPLEX CONIROL 164 301/F 095 Y Y Y -Y Y CHILLER A 11 CHHE-1B CONTROL COMPLEX CONTROL 164 301/G 095 Y Y Y Y Y CIIILLER B 5 CHP-lA CHILLED WATER PUMP A CONIROL 164 NEAR CHHE- 095 Y Y Y .Y Y 1A 5 CHP-1B CHILLED WATER PUMP B CONTROL 164 NEAR CHHE- 095 Y Y Y Y Y IB 21 CHT-1 CHILLED WATER CONTROL 181 302/G ~-

095 Y Y N/A N/A Y EXPANSION TANK Appendix C 10 m

O O O CLASS ID NO. EQUIP DESCRIPTION BLDG E ROOM BASE' CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK' 7 ' CHV-068 SERVICE WATERTO CHHE- CONIROL 172 301/F 095 Y Y N/A Y .Y l A CONTROL VALVE 7 CHV-068-POS CHV-68 CONTROL CONIROL 164 302/F 095 Y Y N/A Y Y 7 CHV-069 SERVICE WA7ER TO CHHE- CONTROL 172 301/F 095 Y Y N/A Y Y-

. IB CONTROL VALVE 7 CHV-069-POS CHV-69 CONTROL CONIROL 164 302/G 095 Y Y N/A Y Y 8B CHV-090 NORMAL COOLING TO AHHE CONTROL 124 304/G 095 Y Y N/A Y Y 44 ISOLATION VALVE 8B CHV-097 APPX. R COOLING FROM CONTROL 125 304/G 095 Y Y N/A Y Y AHHE-44 ISOLATION VALVE 7 CHV-100 AHHE-44 (EFIC ROOMS) CCNTROL 125 304/G 095 Y Y- N/A Y Y CONTROL VALVE 7 CHV-100-POS CHV-100 CONTROL CONTROL 124 303/F 095 Y Y N/A Y Y 8B CHV-100-SV CHV-LOO CONTROL CONTROL 124 303/F 095 Y Y N/A Y Y 8B CHV-101 NORMAL COOLING FROM CONTROL 124 304/G 095 Y Y N/A Y Y AHHE-44 ISOLATION VALVE 8B CliV-108 NORMAL COOLING TO AHHE- CONTROL 131 304/G 095 Y Y N/A Y Y-43 ISOLATION VALVE 7 CHV-113 AHHE-43 (EFIC ROOMS) CONTROL 130 304/G 095 Y Y N/A Y Y CONTROL VALVE 7 CHV-Il3-POS CHV-Il3 CONTROL CONIROL 124 304/G 095 Y Y N/A Y Y 8B CHV-Il3-SV CHV-Il3 CON 1ROL CONIROL 124 304/G 095 Y Y N/A Y Y 18 DC-05-PT DCP-I A DISCHARGE AUXILIARY 095 306/S 095 Y Y Y Y Y 18 DC-06-PT DCP-1B DISCHARGE AUXILIARY 095 306/S 095 Y Y Y Y Y PRESSURE ..

Appendix C 11-

(

' h, ~. b i

CLASS 'ID NO EQUIF DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUEF L 'RC EL OK OK OK OK OK .

18 DC-50-LT DC SURGE TANK DCT-IA AUXILIARY 095 306/S 095 Y Y Y Y Y-LEVEL 18 DC-54-LT DC SURGE TANK DCT-1B AUXILIARY 095 306/T 095 Y Y Y Y Y-Ir s 21 DCHE-1A DECAY HEAT CLOSED AUXILIARY 095 304/P 095 Y Y N/A N/A Y

- CYCLE COOLING A 21 DCHE-1B DECAY HEAT CLOSED AUXILIARY 095 306/P 095 Y Y N/A N/A -Y CYCLE COOLING B 5 DCP-1 A DECAY HEAT CLOSED AUXILIARY 095 306/S 095 Y Y Y Y Y CYCLE COOLING PUMP A 5 DCP-1B DECAY HEAT CLOSED AUXILIARY 095 306fr 095 Y N Y Y N CYCLE COOLING PUMP B 21 DCT-1 A DECAY HEAT CCC SURGE AUXILIARY 095 306/S 095 Y Y N/A N/A Y TANK A 21 DCT-1B DECAY HEAT CCC SURGE AUXILIARY 095 306/S 095 Y Y N/A N/A Y TANK B 7 DCV-186 NITROGEN SUPPLY TO DCT- AUXILIARY 095 307/S 095 Y Y N/A Y Y IA 7 DCV-188 NITROGEN SUPPLY TO DCT- AUXILIARY 095 307/S 095 Y Y N/A Y Y IB 7 DCV-190 DCT-I A OVERPRESSURE AUXILIARY 095 306/S 095 Y Y N/A Y Y CONTROL VALVE 1 7 DCV-191 DCT-1B OVERPRESSURE AUXILIARY 095 306/S 095 Y Y N/A Y Y CONTROL VAVLE 18 DF-1-LS DIESEL GENERATOR FUEL DIESEL I19 119 Y Y Y' Y Y OIL DAY TANK A LEVEL SWITCH Appendix C 12 ,

i t_-. _ - _ . _ -. _ _ _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ - - _ - - - - -_

~

r b b b CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP .CAV ANCH INTER EQUIF L RC EL OK OK OK OK OK 18 DF-2-LS DIESEL GENERATOR FUEL DIESEL 119 119 Y Y Y Y Y OIL DAY TANK A LEVEL SWITCH 18 DF-3-LS DIESEL GENERATOR FUEL DIESEL i19 119 Y Y Y Y Y OIL DAY TANK B LEVEL SWITCH 18 DF-4-LS DIESEL GENERATOR FUEL DIESEL 119 119 Y Y Y Y Y OIL DAY TANK B LEVEL SWITCH

$ DFP-1A AS MOTOR DRIVEN FUEL OIL DIESEL 119 119 Y Y Y Y Y TRANSFER PUMP A 5 DFP-1B AC MOTOR DRIVEN FUEL OIL DIESEL 119 119 Y. Y Y Y Y TRANSFER PUMP B 5 DFP-IC DC MOTOR DRIVEN FUEL OIL AUXILIARY I19 095 Y Y Y Y Y TRANSFER PUMP C 5 DFP-ID DC DRIVEN FUEL OIL AUXILIARY. 119 095 Y Y Y Y Y TRANSFER PUMP D 21 DFT-IA DIESEL GENERATOR FUEL SOUTli 105 105 Y Y N/A N/A Y OIL STO$tAGE TANK A BERM 21 DFT-1B DIESEL GENERATOR FUEL SOUTil 105 105 Y Y N/A N/A Y OIL STORAGE TANK B BERM 21 DFT-3A DIESEL GENERATOR FUEL DIESEL i19 119 Y N N/A N/A N OIL DAY TANK A 21 DFT-3B DIESEL GENERATOR FUEL DIESEL 119 119 Y N N/A N/A N OIL DAY TANK B 18 DH-07-LT BORATED WATER STORAGE BWST 119 307/Q 119 Y Y Y Y Y TANK LEVEL 18 DH-07-LTI BORATED WATER STORAGE BWST 119 307/P ..,

119 Y Y Y Y Y TANK LEVEL Appendix C 13

.- ~ - f.

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH IN11R . EQUIP '

L RC EL - OK ' OK~ OK OK OK-18 DH-37-LT BORATED WATER STORAGE NAOHTANK 119 119 Y Y Y Y- Y TANK LEVEL 21 DHHE-IA DECAY HEAT REMOVAL AUXILIARY 075 304/P4 095 Y Y N/A N/A Y HEATEXCHANGER A 21 DHHE-1B DECAY HEAT REMOVAL AUXILIARY 075 306/P-Q 095 Y Y N/A N/A Y HEAT EXCHANGER B ,

5 DHP-IA DECAY HEAT PUMP A AUXILIARY 075 305/Q 095 Y Y Y Y Y 5 DHP-1B DECAY HEAT PUMP B AUXILIARY 075_ 305/Q 095 Y Y Y Y Y-21 DHT-1 BORATED WATER STORAGE SOUTH 119 119 Y N N/A - N/A' - N TANK BERM 21 DLHE-IA DIESEL GENERATOR LUBE DIESEL 119 301/Q 119 Y Y N/A N/A Y OIL COOLER I A 21 DLHE-1B DIESEL GENERATOR LUBE DIESEL 119 301/Q 119 Y Y N/A N/A Y OIL COOLER IB 21 DLHE-2A DIESEL GENERATOR LUBE DIESEL 119 301/Q l19 Y Y N/A N/A Y OIL COOLER 2A 21 DLHE-2B DIESEL GENERATOR LUBE DIESEL 119 301/Q l19 Y Y N/A N/A Y OIL COOLER 2B 15 DPBA-I A 250/125V BATTERY A CONTROL 108 301/F 095 Y N Y Y N 15 DPBA-1B 250/125V BATTERY B CONTROL 108 302/F 09', Y N Y Y N 15 DPBA-IC 250/125V BATTERY C TURBINE 095 304/A 095 Y N Y U N 16 DPBC-IA BATTERY CHARGER A CONTROL 108 301/G 095 Y Y Y .Y Y 16 DPBC-1B BATTERY CHARGER B CONTROL 108 302/G 095 Y Y Y ~Y 'Y 16 DPBC-IC BATIERY CHARGER C CONTROL 108 301/G 095 .- Y Y Y Y Y 16 DPBC-ID BATTERY CHARGER D CONTROL 108 302/G '

095 Y Y Y Y Y ,

Appendix C 14

n yw (m N] /

CIJ s ID NO EQUIF DESCRIPTION BLDG E ROOM BASE CAF CAV . ANCH INTER EQUIF L RC EL OK OK OK ,OK OK 16 DPBC-lE BATIERY CHARGER E CONTROL 108 302/G 095 Y Y Y Y Y 16 DPBC-IF BATIERY CHARGERF CON 1ROL 108 302/G 095 Y Y Y Y Y 16 DPBC-lG BATIERY CHARGER G TURBINE 095 304/B 095 Y U U N- N 16 DPBC-lH BATIERY CHARGER H TURBINE 095 304/B 095 Y U U N N

'16 DPBC-1I BATIERY CHARGERI TURBINE 095 304/B 095 Y U U N N 14 DPDP-1A 250/125V DC MAIN PANEL 3A CONTROL 108 301/G 095 Y Y Y Y 'Y 14 DPDP-1B 250/125V MAIN PANEL 3B CONIROL 108 303/G 095 Y Y Y Y -Y 14 DPDP-1C 250/125V DC MAIN PANEL 3C TURBINE 095 304/A 095 'Y Y Y N N 14 DPDP-3A 250/125V DC TURBINE TURBINE 095 301/C 095 Y Y Y Y Y BUILDING PANEL A 14 DPDP-3B 250/125V DC TURBNIE TURBINE I19 309/F 095 Y Y Y Y Y-BUILDING PANEL B 14 DPDP-4B CONTROL COMPLEX DC CONIROL 124 302/G 095 Y Y Y Y Y l PANEL 3B l 14 DPDP-5A 250/125V DC ES PANEL A CONTROL 124 303/H 095 Y Y Y Y Y 14 DPDP-5B 250/125V DC ES PANEL B CONTROL 124 303/H 095 Y Y Y Y Y 14 DPDP4A 250/125V DC ES DIESEL DIESEL 119 119 Y Y Y Y Y GENERATOR PANEL A 14 DPDP-6B 250/125V DC ES DIESEL DIESEL 119 119 Y Y Y Y Y GENERATOR PANEL B 14 DPDP-8A 250/125V DC ESSENTIAL CONIROL 108 303/H 095 Y Y Y .Y Y SERVICES PANEL A 14 DPDP-8B 250/125V DC ESSENTIAL CONIROL 108 303/I 095 Y Y Y Y Y SERVICES PANEL B l Appendix C 15 i

V- -- -- __ _ _ _ _ - _ _ _ _ _ _ _ .

. _. . .. _ _. . . . . . _ . . _ . _ . . . _ . . m._

O O O CIASS ID NO EQUEF DESCRIPTION BLDG E ROOM BASE' CAP. _CAV ANCli INTER EQUEF L RC EL OK OK OK 'OK- OK 14 DPDP4C 250/125 VOLT DC EFIC PANEL CONTROL 124 303/1 095 Y Y Y Y' Y D

14 DPDP4D 250/125 VOLT DC EFIC PANEL CONTROL 124 104-H 095 .' Y Y Y Y Y D

14 DPDS-IA BA~ITERY 3A DISCONNECT CONIROL 108 301/G 095 Y Y Y Y Y SWITCH 14 DPDS-1B BATTERY 3B DISCONNECT CONIROL 108 302/G 095 Y Y Y -Y Y SWITCH 14 DPDS-lC BATTERY 3C DISCONNECT TURBINE 095 304/A 095 Y Y Y N N SWITCH 20 DFIP-5A ENGINEERED SAFEGUARDS CONTROL 124 303/H 095 Y Y -Y Y Y DC TEST PANEL 20 DPTP-5B ENGINEERED SAFEGUARDS CONTROL 124 303/H 095 Y Y Y Y Y DC ~EST PANEL 20 DFP?4A ENGINEERED SAFEGUARDS DIESEL i19 119 Y Y Y- Y Y

' DIESEL GENERATOR DC TEST PANEL 20 DirrP 4 B ENGINEERED SAFEGUARDS DIESEL I19 119 'Y Y Y Y Y DIESEL GENERATOR DC TEST PANEL 20 DFTP4A ENGINEERED SAFEGUARDS CONTROL 108 303/H 095 Y Y Y Y Y DC TEST PANEL l 20 DFIP4B ENGINEERED SAFEGUARDS CONTROL 108 303/I 095 Y Y Y Y. Y DC TEST PANEL 2 DPXS-1 MAN XFER SWITCH FOR AUXILIARY 095 303/J 095' Y Y Y Y Y POWERTO MUP-3B AND MUP-SB ,

i 14 DPXS-IC DPBC-I INPUT POWER TURBINE 095 304/A ..,

095 Y N N Y N i TRANSFER SWITCH Appendix C 16 l

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM L BASE ' CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 20 DRRD42 CRD DC BREAKER CABINET CONTROL 124 302/H 095 Y Y Y Y Y 20 DRRD-10 CRD AC BREAKER CABINET CONIROL 124 301/H 095 Y Y Y Y Y A - UNIT 10 20 DRRD-11 ' CRD ACBREAKERCABINET CONIROL 124 301/H 095 .Y Y Y Y- Y B - UNIT 11 20 DRRD-2-1 CRD DC BREAKER CABINET CONTROL 124 302/G 095 Y Y Y N N UNIT I & 2 20 DRRD-2-2 CRD DC BREAKER CABINET CONTROL 124 302/G 095 Y. Y Y U U UNIT 3 & 4 20 DRRD-2-3 CRD DC BREAKER CABINET CONTROL 124 302/G 095 Y Y Y U U TRIP RESET 18 EF-23-FT EFP-1 TO OTSG-B FLOW INTER 095 308/H I19 Y Y Y Y Y 18 EF-24-FT EFP-2 TO OTSG B FLOW INTER 095 307/H I19 Y Y Y' Y Y 18 EF-25-FT EFP-1 TO OTSG A FLOW NER 095 308/H I19 Y Y Y Y Y 18 EF-26-FT EFP-2 TO OTSG A FLOW INTER 095 307/H I19 Y Y Y Y Y 18 EF-98-LT EMERGENCY FEEDWATER EFW TANK I19 119 Y. Y Y Y Y TANK LEVEL 18 EF-99-LT EMERGENCY FEEDWATER EFW TANK I19 119 Y- Y Y Y Y TANK LEVEL 20 EFIC-A EMERGENCY FEEDWATER CONTROL 124 303/F 095 Y Y Y Y Y-INITIATION AND CONTROL CABINET A 20 EFIC-B EMERGENCY FEEDWATER CONIROL 124 302/G 095 Y Y Y Y Y INITIATION AND CONTROL CABINET B Appendix C 17

O O O CIASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP - CAV - ANCH INTER EQUIP L RC EL OK OK- OK OK OK 20 EFIC-C EMERGENCY FEEDWATER CONTROL 124 302/F 095 Y Y Y Y Y INITIATION AND CONTROL 1

CABINET C 20 EFIC-D EMERGENCY FEEDWATER CONTROL 124 303/G 095 Y Y Y- Y Y

l INITIATION AND CONTROL CABINET D 20 EFIC-EC-A EMERGENCY FEEDWATER CONIROL 124 303/F 095 Y' Y Y- Y Y AUXILIARY EQUIPMENT CABINET A 20 EFIC-EC-B EMERGENCY FEEDWATER CONTROL 124 302/G 095 Y Y 'Y Y Y AUXILIARY EQUIPMENT CABINET B 20 EFIC-RC-IC EMERGENCf FEEDWATER CONIROL 124 302/F 095 Y Y Y Y Y AUXILIARY RELAY CABINET IC 20 EFIC-RC-ID EMERGENCY FEEDWATER CONIROL 124' 303/G 095 Y Y Y Y Y AUXILIARY RELAY CABINET ID 5 EFP-1 MOTOR DRIVEN INTER 095 309/G I19 Y Y- Y Y Y-EMERGENCY FEEDWATER PUMP 5 EFP-2 TURBINE DRIVEN INTER 095 308/G 119 Y Y Y Y Y EMERGENCY FEEDWATER PUMP 21 EFT-2 EMERGENCY FEEDWATER EFW TANK 119 119 Y N N/A N/A N TANK 8A EFV-01 HOTWELL ISOLATION TO INTER 095 308/H I19 Y- Y N/A Y Y

'IURBINE DRIVEN EFP-2 8A EFV-02 HOTWELL ISOLATION TO INTER 095 308/H I19 Y Y N/A Y Y MOTOR DRIVEN EFP-1 i

t Appendix C 18 m - . _ - . _ __ ._ __ - ___ _ _ . - _ _ _ _ - - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . . _ ___. _ . - - _ _ _ - - - -

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM ' BASE CAF CAV ANCH INTER EQUIP' L RC EL OK OK OK OK- OK 8A EFV-03 CDT-1 AND EFT-2 ISOLATION INTER 095 308/H 119 Y Y N/A Y' Y TO EFP-1 8A EFV-04 CDT-1 AND SFT-2 ISOLATION INIER 095 308/H I19. Y Y N/A Y- Y

'ID EFP-2 8B EFV-55 EFP-2 TO OTSG B CONTROL INIER 095 307/H I19 Y Y N/A Y Y VALVE 8B EFV-56 EFP-2 TO OTSG A CONTROL INIER 095 306/H I19 Y Y N/A Y Y VALVE 8B EFV-57 EFP-1 TO OTSG B CONTROL INTER 095 308/H I19 Y Y' N/A Y Y VALVE 8B EFV-58 EFP-I TO OTSG A CONTROL INIER I19 307/G 119 Y Y N/A Y Y-VALVE 20 EGCP-1A EMERGENCY DIESEL DIESEL i19 119 Y Y Y Y Y GENERATOR A CONTROL PANEL 20 EGCP-1B EMERGENCY DIESEL DESEL i19 I19 Y Y Y Y Y GENERATOR B CONTROL PANEL 20 EGCP-2A EMERGENCY DIESEL GEN A DESEL i19 119 Y Y- Y N N-ELECTRICAL EQUIPMENT CABINET 20 EGCP-2B EMERGENCY DIESEL GEN B DIESEL' 119 119 Y Y Y N N ELECIRICAL EQUIPMENT CABINET 20 EGCP-3A DIESEL GENERATOR A DESEL i19 /O I19 Y Y Y Y Y CONTROL POWER RELAY CABINET 20 EGCP-3B DIESEL GENERATOR B DESEL 119 /O I19 Y Y Y Y Y CONTROL POWER RELAY ...

CABINET Appendix C 19 m - - . --. _ - . - - _ - ___

s ,s s -

't.) b) b.

. CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 20 EGCP4A DIESEL GENERATOR A DIESEL 119 O I19 Y Y Y Y Y POWER CIRCUIT BITAKER PANEL 20 EGCP4B DIESEL GENERATOR B DESEL 119 /0 119 Y Y Y Y Y POWER CIRCUlT BREAKER PANEL 17 EGDG-1A DIESEL GENERATOR A DESEL 119 119 Y Y Y Y Y 17 EGDG-1B DIESEL GENERATOR B DESEL i19 119 Y Y Y N N 21 EGT-IA EDG A AIR RECEIVER l A DESEL i19 119 Y Y N/A N/A Y 21 EGT-1B EDG A AIR RECEIVER IB DESEL i19 119 Y Y N/A N/A Y 21 EGT-2A EDG B AIR RECEIVER 2A DESEL i19 119 Y Y N/A N/A Y 21 EGT-2B EDG B AIR RECEIVER 2B DESEL i19 119 Y Y N/A N/A Y 8B EGV-36 EDG A AIR START SOLENOID DESEL 119 301/F 119 Y Y N/A Y Y  !

VALVE 8B EGV-37 EDG A AIR START SOLENOID DESEL 119 301/P 119 Y Y N/A Y Y VALVE .

8B EGV40 EDG B AIR START SOLENOID DESEL 119 301/P 119 Y Y N/A Y Y VALVE 8B EGV41 EDG B AIR START SOLENOID DESEL 119 301/P 119 Y Y N/A Y Y ,

VALVE 7 EGV-52 EDG A AIR START 3-WAY DESEL 119' 301/P 119 Y Y N/A Y Y VALVE '

7 EGV-53 EDG A AIR START 3-WAY DESEL 119 301/N 119 Y Y N/A Y Y VALVE 7 EGV-54 EDG B AIR START 3-WAY DESEL 119 301/P 119 Y Y N/A Y Y VALVE ..,

Appendix C 20

._ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ . - - ~

..x fs

-Cl U V CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP -

L RC EL ' OK OK OK OK OK 7 EGV-55 EDG B AIR START 3-WAY DIESEL 119 301/P 119 Y Y. N/A Y Y VALVE 8B EGV-56 EDG A AIR STARTVALVE DIESEL 119 301/P 119 Y Y N/A Y Y 8B EGV-57 EDG A AIR START VALVE DIESEL 119 301/P 119 Y Y N/A Y Y 8B EGV-58 -

EDG B AIR START VALVE DIESEL 119 301/P 119 Y Y- N/A Y Y 8B EGV-59 EDG B AIR START VALVE DIESEL 119 301/P 119 Y Y N/A Y Y 20 ERI EVENTS RECORDER CONTROL 145 302/G 095 Y N N Y N CABINET 1 20 ER2 EVENTS RECORDER CONTROL 145 302/G 095 Y N N Y N CABINET 2 20 ER3 EVENTS RECORDER COKTROL 145 302/G 095 Y N N Y N CABINET 3 20 ER4 EVENTS RECORDER CONTROL I45 302/G 095 Y N N Y N CABINET 4 20 ER5 EVENTS RECORDER CONTROL 145 302/G 095 Y N N Y N CABINET 5 20 ER6 EVENTS RECORDER CONTROL 145 302/G 095 Y N N Y N CABINET 6 20 ER7 EVENTS RECORDER CONTROL 145 302/G 095 Y N N Y N CABINET 7 >

20 ER8 EVENTS RECORDER CONTROL 145 302/G 095 Y N N Y N CABINET 8 20 ESCC-1 ES SYSTEM CHANNEL TEST CONTROL 145 302/G 095 Y Y Y Y Y CABINET 1 20 ESCC-IA ES SYSTEM CHANNEL8 CONIROL I45 302/G 095 Y Y Y Y Y CABINET l A .

Appendix C 21 L . - - -- -- -

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM . BASE ' CAP -- CAV ANCE INTER EQUIP L RC EL OK. .OK OK OK OK 20 ESCC-1B ES SYSTEM CHANNEL CONTROL 145 302/G 095 Y Y Y .Y Y CABINET IB 20 ESCC-2 ES SYSHEM CHANNELDiST CONIROL 145 302/G 095 Y Y Y Y Y CABINET 2 20 ESCC-2A ES SYSTEM CHANNEL CON 1ROL 145 302/G 095 Y Y Y 'Y Y CABINET 2A 20, ESCC-2B - ES SYSTEM CHANNEL CONTROL I45 302/G 095 Y, .Y Y- Y Y CABINET 2B 20 ESCC-3 ES SYSTEM CHANNELTEST CONTROL 145- 302/G 095 Y Y Y Y Y CABINET 3 20 ESCC-3A ES SYSTEM CHANNEL CONTROL 145 302/G 095 Y Y Y Y Y CABINET 3A 20 ESCC-3B ES SYSTEM CHANNEL CONTROL 145 302/G 095 Y Y 'Y Y Y CABINET 3B 20 ESCP-1 MECHANICALINTERLOCK CONIROL 145 301/G 095 Y Y Y Y Y CONTROL BOX 20 ESCP-4A ENGINEERED SAFEGUARDS CONTROL 145 303/H 095 Y Y Y N N ACTUATION RELAY

, CABINET 4A -

20 ESCP-4B ENGINEERED SAFEGUARDS CONIROL 145 303/H 095 Y- Y Y N N ACTUATION RELAY CABINET 4B 20 ESCP-4C ENGINEERED SAFEGUARDS CONTROL 145 303/H 095 Y Y Y N N ACIUATION RELAY CABINET 4C 20 ESCP-4D ENGINEERED SAFEGUARDS CONIROL I45 303/H 095 Y Y Y N N ACTUATION RELAY CABINET 4D 1

Appendix C 22-

^ ~ ~ ~

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP .CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK ,

20 ESCP-5A ENGINEERED SAFEGUARDS CONTROL 145. 303/H 095 Y -Y Y N N ACTUATION RELAY CABINET 5A 20 ESCP-5B . ENGINEERED SAFEGUARDS CCNIROL 145 303/H 095 Y Y Y Y Y ACTUATION RELAY CABINET 5B 'i 20 ESCP-5C ENGINEERED SAFEGUARDS CONIROL 145 303/H 095 Y Y' Y Y Y ACIUATION RELAY CABINET SC 20 ESCP-5D ENGINEERED SAFEGUARDS CONIROL 145 303/H 095 Y- Y Y Y Y ACTUATION RELAY CABINET SD 20 ESPSC-3Al ENGINEERED SAFEGUARDS INTER 095 305/H I19 Y Y Y Y Y PRESSURE SWITCH CABINET 3Al 20 ESPSC-3A2 ENGINEERED SAFEGUARDS INIER 095 305/H I19 Y Y Y Y Y PRESSURE SWITCH CABINET 3A2 20 ESPSC-3A3 ENGINEERED SAFEGUARDS INIDt 095 306/G 119 Y Y Y Y Y PRESSURE SWITCH CABINET 3A3 20 ESPSC-3A4 ENGINEERED SAFEGUARDS AUXILIARY 095 306/N 095 Y Y Y Y Y PRESSURE SWITCH CABINET 3A4 20 ESPSC-3B1 ENGINEERED SAFEGUARDS INTER 095 305/H 119 Y -Y Y -Y Y PRESSURE SWITCH CABINET 3B1 20 ESPSC-3B2 ENGINEERED SAFEGUARDS INTER 095 305/H I19 Y Y .Y Y Y PRESSURE SWTTCH CABINET 3B2 Appendix C 23

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP- CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 20 ESPSC-3B3 ENGINEERED SAFEGUARDS INTER 095 306/G 119 Y Y Y Y Y PRESSURE SWITCH CABINET 3B3 20 FSCP-1 CONTROL PANEL WITH COtGROL 145 095 Y Y Y Y Y BATTERY RACK AND MODULES 20 FSCP-2 LEASED LINE ANNUNCIATOR AUXILIARY 095 303/1 095 Y Y Y. Y Y 20 FSCP-3 LEASED LINE ANNUNCIATOR CONTROL 145 095 Y Y Y Y Y 5 FWP-7 AUXILIARY FEEDWATER 1URBINE 095 307/F 095 Y Y Y Y Y PUMP 7 8A FWV-14 FEEDWATERPUMP A TURBINE 121 309/E 095 Y Y N/A Y Y SUCTION ISOLATION VALVE 8A FWV-15 FEEDWATER PUMP B TURBINE 121 309/E 095 Y Y N/A Y Y SUCTION ISOLATION VALVE 8A FWV-28 FEEDWATER PUMPS TURBINE 109 307/F 095 Y Y N/A Y Y DISCHARGE CROSSTIE ISOLATION VALVE 8A FWV-29 OTSG B MAIN BLOCK VALVE INTER 142 309/G 119 Y Y N/A Y Y 8A FWV-30 OTSG A MAIN BLOCK VALVE INTER 136 310/G 119 Y Y N/A Y Y 8A FWV-31 OTSG A LOW LOAD BLOCK INTER 136 310/G 119 .Y Y N/A Y Y VALVE i

( 8A FWV-32 OTSG B LOW LOAD BLOCK INIER 136 309/G 119 Y Y N/A Y Y l

VALVE 8A FWV-33 OTSG B STARTUP BLOCK INTER 136 309/G 119 Y Y N/A Y Y l VALVE 8A FWV-36 OTSG A STARTUP BLOCK INIER 136 309/G 119 Y U N/A U U VALVE .._

Appendix C 24

v V CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE - CAP- -CAV ANCH INTER EQUIP.

L RC EL OK OK OK OK OK 5 GWP-IA CONDENSNIEINJECTION TURBINE 095 310/E 095 Y Y Y Y- Y PUMP 3A 5 GWP-1B CONDENSATE INJECTION TURBINE 095 310/E 095 Y Y Y Y Y-PUMP 3B 7 GWV-l% GWP-1A CONTROL VALVE TURBINE 095 311/E 095 .Y Y N/A Y Y 20 HTCP-2 EDG-B EMERGENCY LOAD AUXILIARY 095 302/N 095 Y Y Y Y 'Y SHEDDING -HEAT TRACING 20 ffrCP-3 EDG-B EMERGENCY LOAD AUXILIARY I19 302/M 095 Y Y Y Y Y SHEDDING - HEAT TRACING 20 ifrCP-4 EDG-A EMERGENCY LOAD AUXILIARY 095 301/L 095 Y Y Y Y Y SHEDDING - HEAT TRACING 20 HTCP-5 EDG-A EMERGENCY LOAD AUXILIARY 119 301/M 095 Y Y Y Y Y SHEDDING -IEAT TRACING 20 HVAC-16A HVAC CONTROL CABINET AUXILIARY 095 306/T 095 Y Y Y Y Y 16A 20 HVAC-16B HVAC CONTROL CABINET AUXILIARY 095 306/r 095 Y Y Y Y Y 16B 20 HVAC-17A HVAC CONTROL CABINET AUXILIARY 119 304/1 095 Y Y Y Y Y 17A 20 HVAC-17B HVAC CO!GROL CABINET AUXILIARY I19 304/1 095 Y Y Y Y Y 17B 20 HVAC-19 HVAC CONTROL CABINET 19 DIESEL 119 119 Y Y Y Y Y 20 HVAC-20 HVAC CONTROL CABINET 20 DIESEL I19 119 Y Y Y Y Y 18 IA-04-PT INSTRUMENT AIR HEADER TURBINE 095 302/A 095 Y Y Y Y Y PRESSURE Appendix C 25

CLASS ID NO EQUIF DESCRIPTION BLDG E ROOM BASE CAF -CAV ANCH INTER EQUEF -

L RC EL OK OK. OK OK OK 18 IA-12-PS INSTRUMENT AIR TURBINE 095 303/A 095 Y Y Y Y Y COMPRESSOR LOAD /UNIDAD PRESS SWITCH 21 IADR-1 INSTRUMENT AIR DRYER 1 TURBINE 095 302/A 095 Y Y N/A- Y 21 IAHE-1A INSTRUMENT AIR AFTER- TURBINE 095 302/A 095 Y Y N/A Y COOLER A 21 IAHE-1B INSTRUMENT AIR AFIER- TURBINE 095 302/A 095 Y Y N/A Y COOLER B 12 IAP-1A INSTRUMENT AIR TURBINE 095 302/A 095 Y Y Y N N COMPRESSOR A 12 IAP-1B INSTRUMENT AIR TURBINE 095 302/A 095 Y. Y Y Y Y COMPRESSOR B 21 IAT-1A INSTRUMENT AIR RECEIVER TURBINE 095 303/A 095 Y Y N/A Y A

21 IAT-1B INSTRUMENT AIP. RECEIVER TURBINE 095 303/A 095 Y Y N/A Y B

8B IAV-188 IAP-IA LOADER / UNLOADER TURBINE 095 302/A 095 Y Y N/A Y Y VALVE ,

8B IAV-189 IAP-1B LOADER / UNLOADER TURBINE 095 302/A 095 Y Y N/A Y Y VALVE 20 ICS MAIN CONTROL BOARD CONIROL 145 302/F 095 Y Y Y Y Y 20 ICS-1 INTEGRATED CONTROL CONTROL 145 302/F 095 Y Y Y Y Y SYSTEM CABINET I 20 ICS-2 INTEGRATED CONTROL CONTROL 145 302/F 095 Y Y .Y Y Y SYSTEM CABINET 2 ,

20 ICS-3 INTEGRATED CONTROL CONTROL I45 302/F 095 Y Y Y Y Y SYSTEM CABINET 3 Appendix C 26 m- _ - - - -- _ -_.- _ --.------- _ _ _..____ _. _

O O O CLASS 'ID NO EQUIP DESCRIPTION BLDG E ROOM' BASE CAP ~ CAV ANCH INTER . EQUIP L RC- EL OK OK OK OK OK' 20' ICS-4 INTEGRA1ED CONTROL CONTROL 145- 302/F 095 Y Y Y -Y Y SYSTEM CABINET 4 20 ICS-5 INIEGRATED CONTROL CONTROL 145 302/F 095 Y N Y Y .N SYSTEM CABINET 5 18 MS-106-PT MAIN STEAM LINE A-2 INIER I19 309/G 119 Y Y. Y' Y 'Y

~

PRESSURE TRANSMITIER 18 MS-107-Fr MAIN STEAM LINE A-1 INTER 119 309MI 119 Y Y Y Y Y PRESSURETRANSMITIER 18 - MS-108-FT MAIN STEAM LINE A-2 INTER 119 309/G 119 Y Y Y Y- Y PRESSURE TRANSMITTER

- 18 MS-109-PT MAIN STEAM LINE A-1 INTER 119 309MI 119 Y Y Y Y Y PRESSURE TRANSMITTER

, 18 MS-110-PT MAIN STEAM LINE B-2 INIER 119 310/I1 119 Y Y Y Y Y PRESSURE TRANSMITIER 18 MS-Ill-PT MAIN STEAM LINE B-1 INTER 119 310/12 119 Y Y Y Y Y PRESSURE TRANSMITIER 18 . MS-Il2-PT MAIN STEAM LINE B-2 INTER 119 310/11 119 Y Y Y Y Y PRESSURE TRANSMITIER 18 MS-Il3-FF MAIN STEAM LINE B-1 INTER 119 310/J2 119 Y Y Y Y Y PRESSURE TRANSMrrIER 7 MSV-025 ATMOSPHERIC DUMP VALVE INTER I19 309M i19 Y Y N/A Y Y A

7 MSV-026 ATMOSPHERIC DUMP VALVE INTER 119 310/K 119 Y Y N/A .Y' Y .

B 7 MSV433 MAIN STEAM LINE A-2 INTER I19 309M 119 Y Y N/A Y Y SAFETY VALVE 7 MSV-034 MAIN STEAM LINE A-1 INIER I19 309/K '

119 Y Y N/A Y Y SAFETY VALVE -

Appendix C 27

-e1-

, , - - , - - - _ - - - - - - _ _ - - _ - - - --- -----__--u- - - - - _ - _ - - - _ - _ - - _ - - - _ - - - - - - - _ _ _

p (y ,-~

v V V CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 7 MSV-035 MAIN STEAM LINE B-1 INTER 119 310/H I19 Y Y N/A. Y Y SAFETY VALVE 7 MSV-036 MAIN STEAM LINE B-2 INTER I19 310E I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-037 MAIN STEAM LINE A-2 INTER 119 309/H I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-038 MAIN STEAM LINE A-1 INTER I19 309E I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-039 MAIN STEAM LINE B-1 INIER I19 310/H I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-040 MAIN STEAM LINE A-1 INTER 119 309K 119 Y Y N/A Y Y SAFETY VALVE 7 MSV-041 MAIN STEAM LINE B-2 INTER 119 310/K I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-042 MAIN STEAM LINE A-2 INTER I19 309/H I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-043 MAIN STEAM LINE A-1 INTER 119 309/K 119 Y Y N/A Y Y SAFETY VALVE 7 MSV-044 MAIN STEAM LINE B-1 INTER I19 310/H I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-045 MAIN STEAM LINE B-2 INTER 119 310/K 119 Y Y N/A Y Y SAFETY VALVE 7 MSV-046 MAIN STEAM LINE A-2 INTER 119 309/H I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-047 MAIN STEAM LINE B-1 INTER I19 310/H I19 Y Y N/A Y Y SAFETY VALVE 7 MSV-048 MAIN STEAM LINE B-2 INIER I19 310/K 119 Y Y N/A Y Y

^

SAFETY VALVE Appendix C 28 M_ __ __ _ _ _ _ _ _ .- . _ _ _

CLASS ID NO EQUIF DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUEF L RC EL' OK OK OK OK OK 8A MSV-055 OTSG A TO EFTB-1 STOP INTER 119 309/H 119 Y Y N/A Y Y CHECK 8A MSV-056 OTSG B TO EFIB-1 STOP INTER 119 310/K 119 Y Y N/A- Y Y CHECK 7 MSV411 MAIN STEAM LINE A-2 INTER I19 309/G 119 Y Y N/A N N ISOLATION VALVE 21 MSV-411-ARI MSV-411 AIR RESERVOIR I INTER I19 309/G 119 Y Y N/A N/A Y 21 MSV-411-AR2 MSV-411 AIRRESERVOIR2 INTER 119 309/G 119 Y Y N/A N/A Y 21 MSV-411-AR3 MSV-411 AIRRESERVOIR3 INIER I19 309/G 119 Y Y N/A N/A Y 119. 309/G Y Y 8B MSV-411-SV1 MSV-411 CONTROL INTER 119 Y N/A Y 8B MSV-411-SV2 MSV-411 CONTROL INIER 119 309/G 119 Y Y N/A Y Y 8B MSV-411-SV4 MSV-411 CONTROL INTER 119 309/G 119 Y Y N/A Y Y 8B MSV-411/412- MSV-411 & MSV-412 INTER 119 309/G 119 Y Y N/A Y Y SV5 CONTROL 8B MSV-411/412- MSV-411 & MSV-412 INTER 119 309/G 119 Y Y N/A Y Y SV6 CONTROL 7 MSV-412 MAIN STEAM LINE A-1 INTER 119 309/G 119 Y Y N/A Y Y ISOLATION VALVE 21 MSV-412-ARI MSV-412 AIR RESERVOIR I INIER 119 309/G 119 Y Y N/A N/A Y 21 MSV-412-AR2 MSV-412 AIR RESERVOIR 2 INTER 119 309/G 119 Y Y N/A N/A Y 21 MSV-412-AR3 MSV-412 AIR RESERVOIR 3 INTER 119 309/G I19 Y Y N/A N/A Y 8B MSV-412-SV1 MSV-412 CONTROL INTER 119 309/G 119 Y Y N/A Y Y 8B MSV-412-SV2 MSV-412 CONTROL INIER 119 309/G 119 Y Y N/A Y Y 8B MSV-412-SV4 MSV-412 CONTROL INTER 119 309/G ~-

119 Y Y N/A Y Y Appendix C 29 l

~

.s g

.) Y CLASS ID N3 EQUIP DESCRIPTION ELDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 7 MSV-413 MAIN STEAM LINE B-1 INTER 119 310/K 119 Y Y N/A Y Y ISOLATION VALVE 21 MSV-413-AR1 MSV-413 AIRRESERVOIR1 INTER 119 310/K 119 Y Y N/A N/A Y 21 MSV-413-AR2 MSV-413 AIRRESERVOIR2 INIER 119 310/K 119 Y Y N/A N/A Y 21 MSV-413-AR3 MSV-413 AIRRESERVOIR3 INTER 119 310/K 119 Y Y N/A N/A Y 8B MSV-413-SV1 MSV413 CONTROL INIER 119 311/J2 119 Y Y N/A Y Y 8B MSV-413-SV2 MSV-413 CONTROL INTER 119 311/J2 119 Y Y N/A Y Y 8B MSV-413-SV4 MSV-413 CONTROL INTER 119 311/J2 119 Y Y N/A Y Y 8B MSV-413/414- MSV-413 & MSV-414 INTER 119 311/J2 119 Y Y N/A Y Y SV5 CONTROL 8B MSV-413/414- MSV-413 & MSV-414 INTER 119 311/J2 119 Y Y N/A Y Y SV6 CONTROL 7 MSV-414 MAIN STEAM LINE B-2 INTER I19 310/J l19 Y Y N/A Y Y ISOLATION VALVE 21 MSV-414-ARI MSV-414 AIR RESERVOIR I INTER I19 310/J l19 Y Y N/A N/A Y 21 MSV-414-AR2 MSV-414 AIR RESERVOIR 2 INTER I19 310/J l19 Y Y N/A N/A Y 21 MSV-414-AR3 MSV-414 AIR RESERVOIR 3 INTER 119 310/J 119 Y Y N/A N/A Y 8B MSV-414-SV1 MSV414 CONTROL INTER 119 311/J2 119 Y Y N/A Y Y 8B MSV-414-SV2 MSV-414 CONTROL INIER 119 311/J2 119 Y Y N/A Y Y 8B MSV-414-SV4 MSV-414 CONTROL INTER 119 311/J2 119 Y Y N/A Y Y 20 MTCP-1A UNDERVOLTAGE TEST CONTROL 108 303/H 095 Y Y Y Y Y CABINET A 20 MTCP-1B UNDERVOLTAGE TEST CONIROL 108 303/H 095 Y Y Y Y Y CABINET B Appendix C 30

j .

g .

3

! G' J ).

CLASS ID NO EQUE DESCRIPTION BLDG E ROOM BASE CAF CAV - ANCH INTER EQUEF L RC EL - OK OK. OK OK OK 1 MTMC-03 480V ES MCC 3Al AUXILIARY 095 301E 095 ,Y Y Y Y Y-  ;

Y Y Y Y Y 1 MTMC-04 480V ES MCC 3A2 AUXILIARY I19 301/L 095 l MIMC45 480VES MCC3B1 AUXILIARY I19 301/0 095 Y- Y Y- Y Y l

1 MIMC 480V ES MCC 3B2 AUXILIARY 095 304/N 095 Y Y Y Y Y 1 MTMC-07 480V ES MCC 3AB AUXILIARY 119 304/O 095 Y Y Y Y Y I MTMC-08 480V PRESSURIZER HEATER INTER I19 307/G 119 Y Y Y Y Y MCC3A 1 MTMC-09 480V PRESSURIZER HEATER INIER I19 308/G 119 Y N N Y N

MCC 3B  ;

I MIMC-12 480VTURBINE MCC 3A TURBINE I19 304/F 095 Y N N U N 1 MTMC-18 480V REACTOR MCC-3A2 AUXILIARY 095 302K 095 Y Y Y Y Y I MTMC-21 480V ES MCC 3A3 AUXILIARY 119 301/K 095 Y- -Y' Y Y Y I MINC-22 480V ES MCC 3B3 AUXILIARY 095 302/1 095 Y Y Y- Y Y 3 MTSW-2C 4160V ES 3A (NORT11) CONTROL 108 302/G 095 Y U Y N N 3 MTSW-2D 4160V ES 3A(SOUTH) CONTROL 108 302/G 095 Y U Y Y U 3 MTSW-2E 4160V ES 3B (NORTH) CONTROL 108 302/H 095 Y U Y Y U 3 MTSW-2F 4160V ES 3B (SOUTH) CONTROL 108 303/H . 095 Y- U Y N N 2 MTSW-3A 480VTURBINE AUXILIARY TURBINE 095 301/C 095 Y N N Y N BUS A 2 MTSW-3C 480V REACTOR AUXILIARY TURBINE 095 301/D 095 Y N 'N Y- N BUS A 2 MTSW-3D 480V REACTOR AUXILIARY TURBINE 095 302/D 095 Y N N Y N BUS B 2 MTSW-3F 480V ES BUS 3A CONTROL 124 302/H 095 Y N :Y Y N Appendix C 31

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV AMCH INTER EQUEF L RC EL OK OK OK OK OK 4 MTSW-3F-T 4160/480V ES BUS 3A CON 1ROL 124 302M 095 Y. N Y Y N TRANSFORMER 2 MTSW-3G 480V ES BUS 3B CONTROL 124 303M 095 Y N Y Y N 4 hfrSW-3G-T 4160/480V ES BUS 3B CONTROL 124 303M 095 Y N' Y Y N TRANSFORMER 2 MTSW-3J 480V PLANT AUXILIARY BUS TURBINE 095 301/E 095 Y N N Y N 4 MTSW-3J-T 4160/480V PLANT AUXILIARY TURBINE 095 301/E 095 Y N N Y N BUS TRANSFORMER 2 MTXS-1 ES MCC 3AB INPUT POWER CONIROL 124 303M 095 Y U U Y U TRANSFER SWTTCH 18 MU-002-FT PRESSURE TO RCP SEALS AUXILIARY 095 304/K 095 Y Y Y Y Y 7 MU-003-POC MUV-51 CONTROL AUXILIARY 119 304B/L 095 Y Y N/A Y Y 8B MU-003-SV MUV-51 AIR FAIL LOCK AUXILIARY 119 305/P 095 Y Y N/A .Y Y 18 . MU-004-DPT LET-DOWN FLOW AUXILIARY I19 305/P 095 Y Y Y Y Y TRANSMITIER 18 MU-004-DPTl LET-DOWN FLOW AUXILIARY 119 305/O 095 Y Y Y Y Y TRANSMITIER 19 MU-005-TE LETDOWN LINE AUXILIARY I19 305/O 095 Y Y N/A Y Y TEMPERATURE 18 MU-007-DPTl RCP 3Al SEALINJECTION REACTOR 119 NE D-RING 095 Y Y Y Y Y FLOW TRANSMrlTER WALL 18 MU-007-DPT2 REP 3A2 SEAL INJECTION REACTOR I19 N D-RING 095 Y Y Y Y Y FLOW TRANSMITTER WALL 18 MU-007-DPT3 RCP 3B1 SEALINJECTION REACTOR 119 S D-RING 095 Y Y Y Y Y FLOW TRANSMFITER WALL 18 MU-007-DFT4 RCP 3B2 SEAL INJECTION REACTOR I19 SW D-RING 095 Y .Y Y Y Y FLOW TRANSMITTER WALL Appendix C 32

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 0 MU-012-Fr MAKE-UP FLOW AUXILIARY 119 304/M 095 Y N/A N/A Y Y TRANSMITER 7 MU-012-POC MUV-108 CONTROL AUXILIARY 119 304/M 095 Y Y N/A Y Y 18 MU-014-LTl MAKE-UP TANK LEVEL AUXILIARY 'I19 301/L 095 Y Y Y Y Y "IRANSMITTER 18 MU-014-LT2 MAKE-UP TANK LEVEL AUXILIARY 119 301/L 095 Y Y Y Y Y TRANSMITTER 7 MU-015-POC MUV-16 CONTROL AUXILIARY 095 303/K 095- Y- Y N/A Y Y 8B MU-015-SV MUV-16 AIR FAIL LOCK AUXILIARY 095 304/K 095 Y Y N/A Y Y 18 MU-017-FT MAKE-UP TANK PRESSURE AUXILIARY 119 301/L 095 Y Y Y Y Y ,

TRANSMITTER 18 MU-018-DPT LET-DOWN FILTER DELTA-P AUXILIARY 119 303/L 095 Y Y Y Y Y TRANSMITER 18 MU-023-DPTl HI PRESS INECTION FLOW AUXILIARY 095 304/J 095 Y Y Y Y Y LOOP B-1 18 MU-023-DFF2 HI PRESS INECTION FLOW AUXILIARY 095 304/J 095 Y Y Y Y Y LOOP A-2 18 MU-023-Dirt 3 HI PRESS INECTION FLOW AUXILIARY 095 304/J 095 Y Y Y Y Y LOOP B-2 I 18 MU-023-DFr4 HI PRESS INJECTION FLOW AUXILIARY 095 304/J 095 Y Y Y Y Y LOOP A-1

18 MU-023-Dirr5 HI PRESS INECTION FLOW AUXILIARY 095 304/J 095 Y Y Y Y Y l

LOOP B 18 MU-023-DFF6 HI PRESS INECTION FLOW AUXILIARY 095 304/J 095 Y Y Y Y Y l LOOP A l 18 MU-023-DPT7 HI PRESS INECrlON FLOW AUXILIARY 095 304/J 095 Y Y Y Y Y l LOOP B i

Appendix C 33

G NJ CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 18 MU-023-DFT8 HIPRESS INJECTION FLOW AUXILIARY 095 304/J 095 Y Y Y Y Y LOOP A 18 MU-024-DPT MAKE-UP FLOW AUXILIARY 095 304/K 095 Y Y Y Y Y TRANSMITTER 18 MU-024-DPT2 MAKE-UP FLOW AUXILIARY 095 304/K 095 Y Y Y Y Y TRANSMITTER 7 MU-025-POC MUV-31 CONTROL AUXILIARY 095 303/K 095 Y Y N/A Y Y 8B MU-025-SV MUV-31 AIR FAIL LOCK AUXILIARY 095 304/K 095 Y Y N/A Y Y 18 MU-027-DFT RCP TOTAL SEALINJECTION AUXILIARY 095 304/J 095 Y Y Y Y Y FLOW TRANSMITTER 18 MU-031-FTl RCP 3Al SEAL RETURN FLOW REACTOR 119 N D-RING 095 Y Y Y Y Y TRANSMITTER WALL 18 MU-031-FT2 RCP 2A2 SEAL RETURN FLOW REACTOR 119 N D-RING 095 Y Y Y Y Y TRANSMITTER WALL 18 MU-031-FT3 RCP 3B1 SEAL RETURN FLOW REACTOR 119 S SW D-RING 095 Y Y Y Y Y TRANSMITTER WAL 18 MU-031-FT4 RCP 3B2 SEAL RETURN FLOW REACTOR I19 SW D-RING 095 Y Y Y Y Y TRANSMITTER WALL 18 MU-081-DFT LET-DOWN PRE-FILTER AUXILIARY I19 305/O 095 Y Y Y Y Y DELTA-P TRANSMITTER 18 MU-102-DPI RCP SEAL INJECTION FILTER AUXILIARY 095 305/N 095 Y Y Y Y Y DELTA-P INDICATOR 21 MUDM-IA MAKE-UP AND AUXILIARY 119 304/L 095 Y Y Y Y Y PURIFICATION DEMINERALIZER 1 A 21 MUDM-1B MAKE-UP AND AUXILIARY l19 304/L 095 Y Y Y Y Y PURIFICATION DEMINERALIZER IB Appendix C 34

l p  % -

LJ (0 )

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 21 MUHE-1A LET-DOWN COOLER 3A REACTOR 095 E OlJTSIDE D- 095 Y RIN l 21 MUHE-1B LET-DOWN COOLER 3B REACTOR 095 E OUTSIDE D- 095 Y RIN 21 MUHE-IC LET-DOWN COOLER 3C REACTOR 095 E OLTTSIDE D- 095 Y RIN 21 MUHE-2A RCP SEAL RETURN COOLER AUXILIARY I19 302/L-M 095 Y Y N/A N/A Y 3A 21 MUHE-2B RCP SEAL RETURN COOLER AUXILIARY I19 302/L-M 095 Y Y N/A N/A Y 3B 5 MUP-1 A MAKE-UP AND AUXILIARY 095 303/J 095 Y Y Y N N PURIFICATION PUMP 3A 5 MUP-1B MAKE-UP AND AUXILIARY 095 303/J 095 Y Y Y Y Y PURIFICATION PUMP 3B 5 MUP-IC MAKE-UP AND AUXILIARY 095 303/K 095 Y Y Y Y Y PURIFICATION PUMP 3C 5 MUP-2A MUP-1A MAIN OIL PUMP AUXILIARY 095 303/J 095 Y Y Y Y Y 5 MUP-2B MUP-1B MAIN OIL PUMP AUXILIARY 095 303/K 095 Y Y Y Y Y 5 MUP-2C MUP-IC MAIN OIL PUMP AUXILIARY 095 303/K 095 Y Y Y Y Y 5 MUP4A MUP-1A GEAR OIL PUMP AUXILIARY 095 303/J 095 Y Y Y Y Y 5 MUP4B MUP-1B GEAR OIL PUMP AUXILIARY 095 303/K 095 Y Y Y Y Y 5 MUP-4C MUP-1C GEAR OIL PUMP AUXILIARY 095 303/K 095 Y Y Y Y Y 21 MlJT-1 MAKE-UP TANK AUXILIARY 119 302/L 095 Y Y N/A N/A Y 7 MUV-016 RCP SEALINJECTION FLOW AUXILIARY 095 304/K 095 Y Y N/A Y. Y CONTROL VALVE 8A MUV-018 RCP SEAL ISOLATION VALVE AUXILIARY I19 305/N 095 Y Y N/A Y Y Appendix C 35

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 8A MUV-023 HPINJ CONTROL VALVETO AUXILIARY 095 304/K 095 Y Y N/A Y- Y RCS INLET LINES LOOP A 8A MUV-024 HPINJ CONTROL VALVE 1D AUXILIARY 095 304/K 095 Y Y N/A Y Y RCX INLET LINT.S LOOP A 8A MUV-025 HP INJ CONTROL VALVE TO AUXILIARY 095 304/K 095 Y- Y N/A Y Y RCS INLET LINES LOOP B 8A MUV-026 HP INJ CONTROL VALVE TO AUXILIARY 095 304/L 095 Y Y N/A Y Y RCS INLET LINES LOOP B 8A MUV-027 HPI CONTROL VALVE TO RCS AUXILIARY 095 304/K 095 Y Y N/A Y Y LOOP A 7 MUV-031 MAKE-UP FLOW CONIROL AUXILIARY 095 304/K 095 Y Y N/A Y Y VALVE 7 MUV-049 LET-DOWN FLOW ISOLATION AUXILIARY 095 304/K 095 Y Y N/A Y Y VALVE 8B MUV-049-SV MUV-49 CONIROL AUXILIARY 095 304/i. 095 Y Y N/A Y Y 7 MUV-050 LET-DOWN BLOCK OROFICE AUXILIARY I19 304/L 095 Y Y N/A Y Y ISOLATION VALVE EB MUV-050-SV MUV-50 CONTROL AUXILIARY 108 095 Y Y N/A Y Y 7 MUV-051 LET-DOWN FLOW CONTROL AUXILIARY I19 304/L 095 Y Y N/A N N VALVE 8A MUV-058 HI PRESS INJECTION AUX!LIARY 095 306/P 095 Y Y N/A Y' Y SUCTION FROM BWST 8A MUV-073 BWST TO MUP-1 A & MUP-1B AUXILIARY 095 305/O 095 Y Y N/A Y Y ISOLATION VALVE 7 MUV-090 LETDOWN FILTER MUFL-1B AUXRJARY I19 303/L 095 Y Y N/A Y Y TO MUT-1 ISOLATION VALVE 7 MUV-091 LETDOWN FILTED MUFL-l A AUXILIARY I19 303/L 095 Y Y N/A Y Y TO MUT-1 ISOLATION VALVE Appendix C 36

r3 's eg CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 7 MUV 096 LE7DOWN FILTER MUFL-1 A AUXIIJARY 119 303/L 095 Y Y N/A Y Y INlETISOLATION VALVE 7 MUV-097 LETDOWN FILTER MUFL-1B AUXILIARY I19 303/L 095 Y Y N/A Y Y INLETISOLATION VALVE 8A MUV-100 MUFL-I A/MUFL-1B BYPASS AUXILLARY 119 303/L 095 Y Y N/A Y Y VALVE 7 MUV-103 BORIC ACID PUMP TO MAKE- AUXILIARY I19 304/M 095 Y Y N/A Y Y UP TANK ISOLATION VALVE 8B MUV-103-SV MUV-103 CONTROL AUXILIARY I19 304/M 095 Y Y N/A Y Y 7 MUV-108 BORIC ACID PUMP TO MUT-1 AUXILIARY 119 304/M 095 Y Y N/A Y Y FLOW CONTROL VALVE 8A MUV-112 LETDOWN TO MUT-1 OR WD AUXILIARY I19 304/M 095 Y Y N/A Y Y DIVERTER 7 MUV-116 DEMINERALIZER MUDM-IA AUXILIARY 122 304/L 095 Y Y N/A Y Y ISOLATION VALVE TO LETDOWN FILTER 7 MUV-117 DEMINARALIZER MUDM-1B AUXILIARY 122 304/L 095 Y Y N/A Y Y ISOLATION VALVE TO LE7DOWN FILTER 7 MUV-124 ISOLATION VALVE TO AUXILIARY 124 304/L 095 Y Y N/A Y Y PURIFICATION DEMINERALIZER MUDM-I A 7 MUV-133 ISOLATION VALVE TO AUXILIARY 124 304/M 095 Y Y N/A Y Y DEMINERALIZER MUDM-1B 8A MUV-194 MUFL-2A/MUFL-2B BYPASS AUXILIARY 123 305/O 095 Y Y N/A Y Y VALVE 7 MUV-200 LETDOWN ISOLATION AUXILIARY 124 304/L 095 Y Y N/A N N VALVE TO DEMINERALIZER MUDM-1A Appendix C 37

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC. EL OK OK OK OK OK

7. MUV-201 IEIDOWN ISOLATION AUXILIARY 128 304/L 095 Y Y N/A Y Y-VALVE TO DEMihT. RAT.TZER MUDM-1B 7 MUV-242 - PREFIL'ER MUFL-2A INLET AUXILIARY ' 123 305/P 095 Y Y N/A Y Y ISOLATION VALVE 7 MUV-243 PREFILTER MUFL-2A AUXILIARY 121 305/O 095 Y Y N/A Y Y DISCHARGE ISOLATION VALVE 7 MUV-244 PREFILTER MUFL-2B AUXILIARY 121 305/O 095 Y Y N/A Y Y DISCHARGE ISOLATION VALVE 7 MUV-245 PREFILTER MUFL-2B INLET AUXILIARY 123 305/P 095 Y Y N/A Y Y ISOLATION VALVE 7 MUV-253 REALTOR COOLANT PUMP AUXILIARY I19 305/N 095 Y Y N/A Y Y SEAL BLEEDOFFISOLATION VALVE 3 MUXS-1 4160V ISOLATION SWITCH AUXILIARY 095 303/K 095 Y U Y Y U 21 NGT-XX ADV BACKUP NITROGEN TURBINE 095 095 Y N N SUPPLY TANKS (10) 18 NGV-299 ADV BACKUP NITROGEN TURBINE 095 311/G 095 Y Y Y Y Y SUPPLY VALVE 18 NGV-308 ADV BACKUP NITROGEN TURBINE 095 310/G 095 Y Y Y Y Y SUPPLY VALVE 20 NI&P-Al NI&P SYSTEM CONIROL I45 303/G 095 Y Y Y Y Y SUBASSEMBLY A CABINET 1 20 NI&P-A2 NI&P SYSTEM CONTROL I45 303/G 095 Y Y Y Y Y SUBASSEMBLY A CABINET 2 20 NI&P-BI NI&P SYSTEM CONIROL 145 303/G 095 Y Y Y- Y Y SUBASSEMBLY B CABINET 1 Appendix C 38

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE ' CAF CAV ANCH EUER EQUIP L RC EL OK OK OK OK- OK 20 NIAP-B2 NIAP SYSTEM CONTROL '145 303/G 095 Y Y Y Y Y SUBASSEMBLY B CABINET 2 20 NI&P-Cl NIAP SYSTEM CONIROL 145 303M 095 Y Y Y. Y' Y SUBASSEMBLY C CABINET 1 20 NIAP-C2 NIAP SYSTEM CONTROL 145 303M 095 Y Y Y Y Y SUBASSEMBLY C CABINET 2 +

20 NIAP-D1 NIAP SYSTEM CONIROL 145 303M 095 Y Y Y Y Y SUBASSEMBLY D CABINET I 20 NIAP-D2 NI&P SYSTEM CONTROL 145 303M 695 Y Y Y- N N SUBASSEMBLY D CABINET 2 20 NI-1-A3 PROPORTIONAL COUNTER REACTOR 140 095 Y +

ASSEMBLY 20 NI-2-B3 PROPORTIONAL COUNTER REACTOR 140 095 Y ASSEMBLY 20 NI-3-C3 COMPENSATED ION REACTOR 140 095 Y CHAMBER / ASSEMBLY 20 NI-4-D3 COMPENSATED ION REACTOR 140 095 Y-CHAMBER / ASSEMBLY 20 NNI-I AUXILIARY CONTROL CONTROL 145 302/F 095 Y Y Y Y Y SYSTEM CABINET 1 20 NNI-2 AUXILIARY CONTROL CONTROL 145 302/F 095 Y Y Y Y :Y SYSTEM CABINET 2 20 NNI-3 AUXILIARY CONTROL CONTROL 145 302/F 095 Y Y Y Y Y '

SYSTEM CABINET 3 1 20 NNI-4 AUXILIARY CONTROL CONIROL I45 302/F 095 Y Y Y Y Y SYSTEM CABINET 4 t

20 NNI-5 AUXILIARY CONTROL CONTROL 145 302/F 095 Y N. Y Y N  !

SYSTEM CABINET 5 <

Appendix C 39

m es J- pd D.

CLASS ID NO EQUIP DESCRIPTION ELDG E ROOM' BASE CAF CAV ANCH INTER EQUEF L RC EL OK OK OK OK OK 20 N NI-6 AUXILIARY CONTROL CONTROL 145 302/F 095 Y N Y Y N SYSTEM CABINET 6 20 NNI-7 AUXILIARY CONTROL CONTROL 145 302/F 095 Y Y Y Y Y SYSTEM CABINET 7 20 NNI-8 AUXILIARY CONTROL CONTROL 145 302/F 095 Y Y Y- Y Y SYSTEM CABINET 8 20 NSP NUCLEAR SAMPLE PANEL AUXILIARY 095 304B/H 095 Y Y Y Y Y 20 PORV/ TEMP PORV & TEMPERATURE CONIROL 108 304/H 095 Y N Y U N SATURATION CABINET 18 RC-001-LTl PRESSURIZER LEVEL REACTOR 095 RB-330 095 Y Y Y Y Y TRANSMITTER 18 RC-001-LT2 PRESSURIZER LEVEL REACTOR 095 RB-330 095 Y Y Y Y Y TRANSMTrFER 18 RC-001-LT3 PRESSURIZER LEVEL REACTOR 095 RB-331, NR 095 Y Y Y Y Y TRANSMITTER ELEV 19 RC-002-TEI PRESSURIZERTEMPERATURE REACTOR 139 302/G 095 Y 19 RC-002-TE2 PRESSURIZERTEMPERATURE REACTOR 139 303/H 095 Y 18 RC-003A-PTl REACTORCOOLANTSYSTEM REACTOR 095 RB-330 095 Y Y Y Y Y PRESSURE TRANSMITTER 18 RC-003A-PT2 REACTOR COOLANT SYSTEM REACTOR 095 RC-331 095 Y Y Y Y Y PRESSURE TRANSMITTER 18 RC-003A-PT3 REACTORCOOLANTSYSTEM REACTOR 095 RC-330 095 Y Y Y Y Y PRESSURE TRANSMrITER 18 RC-003A-PT4 REACTOR COOLANT SYSTEM REACTOR 095 RB-331 NR 095 Y Y Y Y Y PRESSURETRANSMITTER ELEV 18 RC-003B-PTl REACTORCOOLANTSYSTEM REACTOR 095 RB-326 095' Y Y Y Y Y PRESSURE TRANShETTER Appendix C 40

O O O CLASS ID NO EQUIF DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUEF L RC EL OK .OK OK OK OK 18 RCA)3B-Pr2 REACTORCOOLANTSYSTEM REACTOR 095 RB-328 095 Y- Y- Y Y Y PRESSURETRANSMITIER 18 RC-003B-PT3 REACTORCOOLANTSYSTEM REACTOR 095 RB-326 095 . Y- Y Y. Y Y~

PRESSURETRANSMITTER 19 RC-004A-TEl - REACTOR COOLANT SYSTEM REACTOR 119 S OF RCSG-1A 095 Y Y N/A Y Y.

HOT LEG A TEMPERATURE 19 RC-004A-TE2 REACTORCOOLANTSYSTEM REACTOR 119 S OF RCSG-I A 095 Y Y N/A- Y Y HOTLEG ATEMPERATURE 19 RC-004A-TE3 REACTORCOOLANTSYSTEM REACTOR I19 S OF RCSG-1 A 095 Y Y N/A- Y Y' HOTLEG ATEMPERATURE 19 RC-004A-TE4 REACTOR COOLANT SYSTEM REACTOR 119 S OF RCSG-IA 095 Y Y N/A. Y Y HOTLEG ATEMPERATURE 19 RC-004B-TEI REACTORCOOLANTSYSTEM REACTOR 119 N OF RCSG-1B 095 Y Y N/A Y Y '

HOT LEG B TEMPERATURE 19 RC-004B-TE2 REACTORCOOLANTSYSTEM REACTOR I19 N OF RCSG-1B 095 Y Y N/A Y- Y HOT LEG B TEMPERATURE 19 RC-004B-TE3 REACTOR COOLANT SYSTEM REACTOR 119 N OF RCSG-1B 095 Y Y N/A Y Y-HOT LEG B TEMPERATURE 19 RC-004B-TE4 REACTORCOOLANTSYSTEM REACTOR 119 N OF RCSG-1B 095 Y Y N/A Y Y I HOT LEG B TEMPERATURE l 19 RC-005A-TEI REACTORCOOLANTSYSTEM REACTOR I19 RCP-1 A 095 Y Y N/A- Y Y _,

l COLD MG A TEMPERATURE 19 RC-005A-TE2 REACTOR COOLANT SYSTEM REACTOR 119 RCP-IA 095 Y Y N/A' Y Y COLD MG B TEMPERATURE i l

~

19 RC-005A-TE3 REACTORCOOLANTSYSTEM REACTOR 119 RCP-1B 095 Y Y N/A Y Y COLD EG B TEMPERATURE 19 RC-005A-TE4 REACTOR COOLANT SYSTEM REACTOR I19 RCP-1B 095 Y Y N/A Y Y COLD LEG A TEMPERATURE Appendix C 41 i

s. 7-.

()

d V CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER - EQUIP L RC EL OK OK OK 'OK OK 19 RC-005B-TEI REACTORCOOLANTSYSTEM REACTOR 119 RCP-IC 095 Y Y- N/A Y Y COLD LEG B TEMPERATURE 19 RC-005B-TE2 REACTORCOOLANTSYSTEM REACTOR 119 RCP-IC 095 Y Y N/A Y Y COLD EG B TEMPERATURE 19 RC-005B-TE3 REACTORCOOLANTSYSTEM REACTOR 119 RCP-ID 095 Y Y N/A Y Y COLD LEG B TEMPERATURE 19 RC-005B-TE4 REACTOR COOLANT COLD REACTOR 119 RCP-ID 095 Y Y N/A Y Y LEG B TEMPERATURE 18 RC-014A-DFTl REACTORCOOLANTSYSTEM REACTOR 095 SE OF RB-330 095 Y Y Y Y Y HOT EG A FLOW 18 RC-014A-DFT2 REACTOR COOLANT SYSTEM REACTOR 095 SE OF RB-331 095 Y Y Y Y Y HOTEG A FLOW 18 RC-014A-DFT3 REACTORCOOLANTSYSTEM REACTOR 095 SE OF RB-331 095 Y Y Y Y Y HOT LEG A FLOW 18 RC-014A-DFF4 REACTOR COOLANT SYSTEM REACTOR 095 N D-RING 095 Y Y Y Y Y HOTLEG A FLOW WALL 18 RC-014B-DPTl REACTOR COOLANT SYSTEM REACTOR 095 RB-326 095 Y Y Y Y Y ,

HOT LEG B FLOW 18 RC-014B-DPT2 REACTOR COOLANT SYSTEM REACTOR 095 RB-328 095 Y Y Y Y Y HOT LEG B FLOW I 18 RC-014B-DFT3 REACTORCOOLANTSYSTEM REACTOR 095 RB-328 095 Y Y Y Y Y '

HOT LEG B FLOW 18 RC-014B-DPT4 REACTORCOOLANTSYSTEM REACTOR 095 RB-326 095 Y Y Y Y Y HOT LEG B FLOW 18 RC-131-FT REACTORCOOLANTSYSTEM REACTOR 095 N D-RING 095 Y Y.' Y Y- Y PRESSURE WALL 18 RC-131-PTl REACTOR COOLANT SYSTEM REACTOR 095 N D-RING 095 Y Y Y Y Y PRESSURE WALL Appendix C 42

_ g. .

l k._.) O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 20 RCCP-1 PRESSURIZER HEATER SCR INTER I19 308/G 119 Y Y Y Y Y CONTROL PANEL 20 RCITS-A REACTOR COOLANT CONTROL 124 302/H 095 Y Y Y Y Y INVENTORYTRACKING SYSTEM CABINET A 20 RCITS-B REACTOR COOLANT CONIROL 124 303/1 095 Y Y Y Y Y INVENTORY TRACKING SYSTEM CABINETi' 20 RCITS-C REACTOR COOLANT CONTROL 124 302/H 095 Y Y Y Y Y INVENTORY TPACKING SYSTEM CABINET C 20 RCPM-3A REACTOR COOLANT PUMP CONIROL 108 303/1 095 Y U N/A N/A U POWER MONTTORING CABINET A 20 RCPM-3B REACTOR COOLANT PUMP CONTROL 108 303/1 095 Y U N/A N/A- U POWER MONITORING CABINET B 20 RCTR-1 RCP-1C TRANSFORhER INTER I19 310/H1 119 Y Y Y Y Y CABINET 20 RCTR-2 RCP-ID TRANSFORhER INTER 119 310/H1 119 Y Y Y Y Y CABINET 20 RCTR-3 RCP-1 A TRANSFORhER AUXILIARY 119 306/H 095 Y Y Y Y Y CABINET 20 RCFR-4 RCP-1B TRANSFORhER INER 119 306/G1 119 Y Y Y Y Y CABINET 8B RCV-10 PRESSURIZER POWER REACTOR 168 307/I 095 N Y N/A Y N OPERATED RELIEF VALVE 8A RCV-11 PRESSURIZER BLOCK VALVE REACTOR 168 307/1 095 N Y N/A Y N Appendix C 43

(

b,-~ d,m CLASS ID NO EQUIP DESCRIPTION BLDG E E.O O M BASE CAF CAV AMCH INTER ~ EQUIP L MC EL OK OK' OK OK OK 8A RCV-13 FRESSURIZERINLET REACTOR 145 307/I 095 Y U-AUXILIARY SPRAY ISOLATION VALVE 8A RCV-53 DH TO PRESSURIZER REACTOR 145 307/1 095 Y Y N/A Y Y AUXILIARY SPRAY ISOLATION VALVE 20 RFL MPLXR RFL MULTIPLEXER FOR 500 CONIROL I45 302/H 095 Y N Y Y N KV SWITCHYARD 20 RNR RECORDER NEST RACK CONIROL 145 095 Y Y Y Y Y 20 RR-HV AUXILIARY RELAY RACK CONTROL 124 301/F 095 Y Y Y Y Y HEATING AND VENTILATION 20 RR-PSA AUXILIARY RELAY RACK CONTROL 124 301/F 095 Y Y Y Y Y 20 RR1 AUXILIARY RELAY RACK CONTROL 124 301/F 095 Y Y Y Y Y 20 RRIA ENGINEERED SAFEGUARD CONTROL 124 301/F 095 Y Y Y Y Y AUXILIARY RELAY RACK RRIA -

20 RRIAB ENGINEERED SAFEGUARD CONTROL 124 301/F 095 Y Y Y Y Y AUXILIARY RELAY RACK RRIAB ,

20 RRIB ENGINEERED SAFEGUARD CONIROL 124 302/F 095 Y Y Y Y Y AUXILIARY RELAY RACK RRIB 20 RR2 AUXILIARY RELAY RACK CONTROL 124 301/F 095 Y Y Y Y Y 20 RR2A ENGINEERED SAFEGUARD CONTROL 124 301/F 095 Y Y Y Y Y AUXILIARY RELAY RACK NA 20 RR2AB ENGINEERED SAFEGUARD CONTROL 124 301/F 095 Y Y Y Y Y AUXILIARY RELAY RACK RR2AB Appendix C 44 l

g s.

-V V ()

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 20 RR2B ENGINEERED SAFEGUARD CONTROL 124 302/F 095 Y Y Y N N AUXILIARY RELAY RACK RR2B 20 RR3 AUXILIARY RELAY RACK CONTROL 124 301/F 095 Y Y Y Y Y 20 RR3A ENGINEERED SAFEGUARD CONIROL 124 301/F 095 Y Y Y Y Y AUXILIARY RELAY RACK RR3A 20 RR3B ENGINEERED SAFEGUARD CONTROL 124 301/F 095 Y Y Y Y Y AUXILIARY RELAY RACK RR3B 20 RR4A POST-ACCIDENT CONTROL 124 303/F 095 Y Y Y Y Y MONITORING PANEL 4A 20 RR4B POST-ACCIDENT CONTROL 124 302/G 095 Y Y Y Y Y MONITORING PANEL 4B 20 RR5BI ENGINEERED SAFEGUARD CONTROL 124 302/G 095 Y Y Y Y Y AUXILIARY RELAY RACK RR5BI 20 RR5B2 ENGINEERED SAFEGUARD CONIROL 124 302/G 095 Y Y Y Y Y AUXILIARY RELAY RACK RR5B2 20 RSA REMOTE SHUTDOWN RELAY CONIROL 108 303/G 095 Y Y Y N N CABINET A 20 RSA-1 REMOTE SHUrDOWN RELAY CONTROL 108 303/G 095 Y Y Y N N CABINET A-1 20 RSACA REMOTE SHUTDOWN CONIROL 108 302/G 095 Y Y Y Y Y AUXILIARY CABINET A 20 RSACB REMOTE SHUTDOWN CONTROL 108 303/G 095 Y Y Y Y Y AUXILIARY CABINET B -

Appendix C 45

CLASS ID NO EQUIP DESCRIPTION ELDG E ROOM BASE CAF CAV ANCH INTER EQUP L RC EL - OK OK OK OK- OK 20 RSB REMOTE SHUIDOWN RELAY ' CONTROL 108 304/G 095 Y Y Y Y Y CABINET B 20 RSB-1 REMOTESHUTDOWNRELAY CONTROL 108 303/G 095 ~Y- Y Y Y. Y CABINET B-1 20 RSPA REMOTE SHUTDOWN CONTROL 108 304/G 095 Y Y Y Y Y PANEL-SECI1ON A 20 RSPAB REMOTE SHUTDOWN CONTROL 108 304/G 095 Y Y Y Y' Y PANEL-SECTION AB 20 RSPB REMOTE SHUrDOWN CONTROL 108 304/G 095 Y Y- Y Y Y PANEL - SECTION B 18 RW48-FT DECAY HEAT SEA WATER AUXILLARY 095 307/R 095 Y Y Y Y Y PUMP B DISCHARGE PRESSURE ,

18 RW-09-FT DECAY HEAT SEA WATER AUXILIARY 095 307/P 095 Y Y Y Y Y PUMP A DISCHARGE PRESSURE 19 RW-12-TE DH SERVICE SEA WATER AUXILIARY 095 306/R 095 Y Y N/A Y Y PUMP RWP-3B DISCHARGE TEMPERATURE 19 RW-13-TE DECAY HEAT SEA WATER AUXILIARY 095 306/P 095 Y Y N/A Y Y PUMP RWP-3A DISCHARGE TEMPERATURE 19 RW-19-TE NUCLEAR SERVICE SEA AUXILIARY 095 306/Q 095 Y Y N/A Y Y WATER PUMP RWP-2B DISCHARGE TEMP 18 RW-23-FT NUCLEAR SERVICE SEA AUXILIARY 095 307/R 095 Y Y Y Y Y WATER PUMPS DISCHARGE PRESSURE 19 RW-32-TE DECAY HEAT COOLER DCHE- AUXILIARY 095 305/T 095 Y Y N/A Y Y IB SEA WATER OUTLET Appendix C 46

O O O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L ~RC EL OK OK OK OK OK 19 RW-33-TE DECAY HEAT COOLER DCHE. AUXILIARY 095 305/r 095 Y Y N/A Y Y 1A SEA WATEROUILET 19 RW-43-TE SEA WATER OUTLET AUXILIARY 095 306/S 095 Y Y' N/A Y Y NUCLEAR SERVICE COOLERS 6 RWP-1 NORMAL NUCLEAR AUXILIARY 095 307Q 095 Y N Y Y N SERVICES SEA WATER PUMP MOTOR COLLER 6 RWP-2A NUCLEAR SERVICE SEA AUXILIARY 095 307/P 095 Y N Y Y N WATER PUMP 3A 6 RWP-2B NUCLEAR SERVICE SEA AUXILIARY 095 307/Q 095 Y N Y Y N WATER PUMP 3B 6 RWP-3A DECAY HEAT SERVICE SEA AUXILIARY 095 307/P 095 Y N Y Y N WATER PUMP 3A 6 RWP-3B DECAY HEAT SERVICE SEA AUXILIARY 095 307/R 095 Y N Y Y N WATER PUMP 3B 21 RWSP-IA CYCLONE SEPARATOR A AUXILIARY 095 SEA WATER 095 Y Y N/A N/A Y ROOM 21 RWSP-1B CYCLONE SEPARATOR B AUXILIARY 095 SEA WATER 095 Y Y N/A N/A Y ROOM 7 RWV-150 RW RECIRCULATION FLOW AUXILIARY 095 307/R 095 Y Y N/A Y Y CONTROL VALVE 21 SAHE-1 A STATION AIR COMPRESSOR TURBINE 095 095 Y Y Y AFTER-COOLER A 21 SAHE-1B STATION AIRE COMPRESSOR TURBINE 095 095 Y Y Y AFTER-COOLER B 12 SAP-1A STATION AIR COMPRESSOR TURBINE 095 095 Y Y Y Y Y 1A 12 SAP-1B STATION AIRCOMPRESSOR TURBINE 095 095 Y Y Y Y Y IB Appendix C 47 L

J R.;

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL' OK OK OK OK OK 5 SCP-3 SECONDARY SERCIVES TURBINE 095 304/G 095 Y Y Y Y Y.

CIDSED CYCLE COOLING BOOSTER PUMP 7 SCV-095 IAP-1 A & 1AHE-I A COOLING TURBINE 108 302/lB 095 Y Y N/A Y Y WATER CONTROL VALVE 7 SCV-0% IAP-1B & IAHE-1B COOLING TURBINE 108 302/B 095 Y Y N/A Y Y WATER CONTROL VALVE 8B SCV-099 IAP-1A & IAHE-1 A COOLING TURBINE 107 302/B 095 Y Y N/A Y Y WATER ISOLATION VALVE 8B SCV-100 1AP-1B &lAHE-IC COOLING TURBINE 107 302/B 095 Y Y N/A Y Y WATER ISOLATION VALVE 18 SF-9-FIT SPENT FUEL COOLANT FLOW AUXILIARY 143 304/K 095 N Y Y Y N TRANSMITTER 21 SFDM-1 SPENT FUEL COOLANT AUXILIARY I19 302/J 095 Y Y N/A N/A Y DEMINERALIZER 21 SFHE-1A SPENT FUEL COOLER A AUXILIARY 119 302/J 095 Y Y N/A N/A Y 21 SFHE-1B SPENT FUEL COOLER B AUXILIARY I19 302/J 095 Y Y N/A N/A Y 5 SFP-IA SPENT FUEL COOLANT PUMP AUXILIARY 119 303/J 095 Y Y Y Y Y A

5 SFP-1B SPENT FUEL COOLANT PUMP AUXILIARY I19 303/J 095 Y Y Y Y Y B

18 SP-17-LT STEAM GENERATOR A LE'dL REACTOR 095 N D-RING 095 Y Y Y Y Y WALL 18 SP-18-LT STEAM GENERATOR A LEVEL REACTOR 095 N D-RING 095 Y Y Y Y Y WALL 18 SP-19-LT STEAM GENERATOR A LEVEL REACTOR 095 N D-RING 095 Y Y Y Y Y WALL Appendix C 48

_ - _ - _ - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _. __- _ _ _ . = _ _ _ _ _ _ _ _ _ _ - _ _ _-

. g~s

'% V CLASS ID NO EQUIP CESCRIPTION F:LDG E ROOM . BASE CAF CAV - ANCH INTER EQUIP L RC EL OK OK OK OK OK 18 SP-20-LT STEAM GENERATOR A LEVEL REACTOR 095 N D-RING 095 Y Y Y Y Y WALL 18 SP-21-LT STEAM GENERATOR B LEVEL REACTOR 095 S D-RING 095 Y Y Y Y Y WALL 18' SP-22-LT STEAM GENERATOR B LEVEL REACTOR .095 RB-328 095 Y Y Y Y Y 18 SP-23-LT STEAM GENERATOR B LEVEL REACTOR 095 S D-RING 095 Y Y Y Y Y WALL I8 SP-14-LT STEAM GENERATOR B LEVEL REACFOR 095 RB-328 095 Y Y Y Y Y 18 SP-25-LT STEAM GENERATOR A LEVEL REACTOR 095 N D-RING 095 Y Y Y Y Y WALL 18 SP-26-LT STEAM GENERATOR A LEVEL REACTOR 095 M D-RING 095 Y Y Y Y Y WALL 18 SP-27-LT STEAM GENERATOR A LEVEL REACTOR 095 N D-RING 095 Y Y Y Y Y WALL 18 SP-28-LT STEAM GENERATOR A LEVEL REACTOR 095 N D-RING 095 Y Y Y Y Y WALL 18 SP-29-LT STEAM GENERATOR B LEVEL REACTOR 095 S D-RING 095 Y Y Y- Y Y' WALL 18 SP-30-LT STEAM GENERATOR B LEVEL REACTOR 095 S "Y" STATION 095 Y Y Y Y Y 18 SP-31-LT STEAM GENERATOR B LEVEL REACTOR 095 S D-RING 095 Y Y Y Y Y WALL 18 SP-32-LT STEAM GENERATOR B LEVEL REACTOR 095 RB-328 095 Y Y Y Y Y 5 SSP-4A CONDENSER A HOTWELL TURBINE 095 306/E 095 Y Y Y Y' Y SAMPLE EXTRACTION PUMP 5 SSP-4B CONDENSER B HOTWELL TURBINE 095 306/E 095 Y Y Y Y Y SAMPLE EXTRACTION PUMP Appendix C 49

O O O _

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 5 SSP-4C CONDENSER AB HOTWELL TURBINE 095 306/E 095 Y Y Y Y .Y CROSSOVER SAMPLE EXTRACTION PUMP 5 SSP-4D LP HEATER SAMPLE TURBINE 095 306/E 095 Y Y Y Y Y EXTRACTION PUMP 18 SW-002-PT NUCLEAR SERVICE CCC AUXILIARY 095 307/P 095 Y Y Y Y Y PUMPS DISCHARGE PRESSURE 18 SW-135-PT NUCLEARSERVICECOOLING AUXILIARY 095 307/S 095 Y Y Y Y Y WATER SURGE TANK PRESSURE 18 SW-139-LT NUCLEAR SERVICE COOLING AUXILIARY 095 307/T 095 Y Y Y Y Y WATER SURGE TANK LEVEL 21 SWHE-1 A NUCLEAR SERVICE CCC AUXILIARY 095 SEA WATER 095 Y Y N/A N/A Y HEAT EXCHANGER 3A ROOM 21 SWHE-1B NUCLEAR SERVICE CCC AUXILIARY 095 SEA WATER 095 Y Y N/A N/A Y IEAT EXCHANGER 3B ROOM 21 SWHE-1C NUCLEAR SF"VICE CCC AUXILIARY 095 SEA WATER 095 Y Y N/A N/A Y HEAT EXC' JGER 3C ROOM 21 SWlE-1D NUCLEAR SERVICE CCC AUXILIARY 095 SEA WATER 095 Y Y N/A N/A Y HEAT EXCHANGER 3D ROOM 21 SWHE-2 SW SUPPLY TO PASS SAMPLE AUXILIARY 108 305/H 095 Y Y N/A N/A Y COOLERS S SWP-i A EMERGENCY NUCLEAR AUXILIARY 095 307/P 095 Y U U Y U SERVICE CCC PUMP 3A 5 SWP-lB EhERGENCY NUCLEAR AUXILIARY 095 307/Q 095 Y U U N N SERVICE CCC PUMP 3B Appendix C 50

G J O CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP L RC EL OK- OK OK OK OK 5 SWP-1C NORMALNUCLEARSERVICE AUXILIARY 095 307/S 095. Y U U Y. U CLOSED CYCLE COOLING PUMP 5 SWP-2A NUCLEAR SERVICE BOOSTER AUXIIJARY 095 305/P 095 -Y Y Y Y Y PUMP A 5 SWP-2B NUCLEAR SERVICE BOOSTER AUXILIARY 095 305/P 095 Y Y Y Y Y PUMP B 21 S W T-1 NUCLEAR SERVICE CLOSED AUXILIARY 095 307/S 095 Y Y N/A N/A Y CYCLE SURGE TANK 7 SWV-012 SEAL RETURN COOLERS AUXILIARY I19 PRE-FILTER 095 Y Y N/A Y Y SUPPLY ISOLATION VALVE AREA 21 SWV-012-AR SWV-12 CONTROL AUXILIARY 119 304/P 095 Y Y Y Y Y.

8B SWV-012-SVI SWV-12 CONTROL AUXILIARY 119 304/P 095 Y Y N/A Y Y SB SWV-012-SV2 SWV-12 CONTROL AUXILIARY 119 304/P 095 Y Y N/A Y Y 7 SWV-035 INLET ISOLATION FOR AIDE- AUXILIARY 095 305/N 095 Y Y 'N/A Y Y 31A AND AHHE-32A 7 SWV-037 INLETISOLATION FOR AHHE- AUXILIARY 095 305/N 095 Y Y N/A Y Y 31B AND AIDE-32B 7 SWV-039 INLET ISOLATION FOR AIDE. AUXILIARY 095 305/N 095 Y Y N/A Y Y 31C AND AIDE-32C 7 SWV-041 ISOLATION FROM OUTLETS AUXILIARY 119 305/N 095 Y Y N/A Y Y OF AIDE-31A AND AHIE-32A 7 SWV-043 OUTLETISOLATION FOR AUXILIARY 095 305/N 095 Y Y N/A Y Y AIDE-31B AND AIDE-32B 7 SWV-045 OUTLET ISOLATION FOR AUXILIARY 095 305/N 095 Y Y N/A Y Y AIDE-31C AND AHHE-32C 7 SWV-047 ISOLATION TO MUHE-1B AUXILIARY 095 305/N 095 Y Y N/A Y Y AND WDHE-1 Appendix C 51

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CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 7 SWV-048 LETDOWNCOOLER3BINLET AUXILIARY 095 305/N 095 Y Y N/A Y Y ISOLATION VALVE 7 SWV-049 LETDOWN COOLER 3B AUXILIARY 095 305/N 095 Y Y N/A Y Y DISCHARGE ISOLATION VALVE 7 SWV-050 OUTLETISOLATION FOR AUXILIARY 095 305/N 095 Y Y N/A Y Y MUHE-1 A AND WDHE-1 7 SWV-151 IC FROM RB FAN COOLERS AUXILIARY 100 SEA WATER 095 Y Y N/A Y Y ISOLATION VALVE ROOM 21 SWV-151-AR AIRRESERVOIRFORSWV-151 AUXILIARY 100 307/O 095 Y Y N/A N/A Y 3B SWV-151-SV SWV-151 CONTROL AUXILIARY 095 307/O 095 Y Y N/A Y Y 7 SWV-152 IC TO RB RAN COOLERS AUXILIARY 100 307/P 095 Y Y N/A Y Y ISOLATION VALVE 21 SWV-152-AR AIR RESERVOIR FOR SWV-152 AUXILIARY 100 305/O 095 Y Y N/A N/A Y 8B SWV-152-SV1 SWV-152 CONTROL AUXILIARY 095 307/O 095 Y Y N/A Y Y 8B SWV-152-SV2 SWV-152 CONTROL AUXILIARY 095 307/O 095 Y Y N/A Y Y 7 SWV-353 SW TO RB FAN COOLERS AUXILIARY 095 307/P 095 Y Y N/A Y Y ISOLATION VALVE 21 SWV-353-AR AIR RESERVOIR FOR SWV-353 AUXILIARY 095 307/P 095 Y Y N/A N/A Y 8B SWV-353-SV1 SWV-353 CONTROL AUXILIARY 095 307/P 095 Y Y N/A Y Y 8B SWV-353-SV2 SWV-353 CONTROL AUXILIARY 095 307/O 095 Y Y N/A Y Y 7 SWV-354 SW FROM RB FAN COOLERS AUXILIARY 095 307/O 095 Y Y N/A Y Y ISOLATION VALVE 21 SWV-354-AR AIRRESERVOIRFORSWV-354 AUXILIARY 095 307/O 095 Y Y N/A N/A Y 8B SWV-354-SV1 SWV-354 CONTROL AUXILIARY 095 307/O 095 Y N N/A Y N Appendix C 52

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L l

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV ANCH INTER EQUIP L RC EL OK OK OK OK- OK 8B SWV-354-SV2 SWV-354 CONIROL AUXILIARY 095 307/O 095 Y N N/A Y N 7 SWV-355 IC FROM RB FAN COOLERS AUXILIARY 095 307/O 095 Y Y. N/A Y Y ISOLATION VALVE 21 SWV-355-AR AIR RESERVOIR FOR SWV-355 AUXILIARY 095 307/O 095 Y Y N/A N/A Y 8B SWV-355-SV SWV-355 CONTROL AUXILIARY 095 307/O 095 Y Y N/A Y Y 20 TPC TRANSMITIERPOWER CONTROL 124 302/F 095 Y N N Y N SUPPLY CABINETS A & B 14 VBDP-01 REGULATED INSTRUhENT CONTROL 145 302/H 095 Y Y Y Y Y BUS 3A 14 VBDP-02 REGULATED INSTRUhENT CONTROL 145 302/H 095 Y Y Y Y Y BUS 3B 14 VBDP-03 VITAL BUS A CONTROL 145 302/H 095 Y Y Y Y Y 14 VBDP-04 VITAL BUS B CONTROL I45 302/H 095 Y Y Y Y Y 14 VBDP-05 VITAL BUS C CONTROL 145 302/H 095 Y Y Y Y Y 20 VBDP-05-SIP 120 VOLT VITAL BUS 3C CONTROL 145 302/H 095 Y Y Y Y Y STATUS INDICATION PANEL 14 VBDP-06 VITAL BUS D CONTROL 145 302/H 095 Y Y Y Y Y 20 VBDP-06-SIP 120 VOLT VITAL BUS 3D CONTROL 145 302/H 095 Y Y Y Y Y STATUS INDICATION PANEL 14 VBDP-07 COMPUTER 120 VAC CONTROL 145 302/F 095 Y Y Y Y Y DISTRIBUTION PANEL 14 VBDP-08 EFIC VITAL BUS A CONTROL 124 303/F 095 Y Y Y Y Y 20 VBDP-08/12/13- VITAL BUS STATUS CONTROL 124 303/F 095 Y Y Y Y Y SIP INDICATION PANEL A FOR VBDP-8/12/13 Appendix C 53

CLASS ID NO EQUIF DESCRIPTION BLDG E ROOM ' BASE CAF CAV ANCH INTER EQUIP i L RC EL' OK OK OK OK OK-

-14 VBDP419 EFIC VITAL BUS C CONTROL 124 302/F 095 Y Y Y Y Y 20 VBDP-09-SIP VITAL BUS STATUS CONTROL 124 302,7 095 Y Y Y Y Y INDICATION PANEL C FOR VBDP-9 14 VBDP-10 EFIC VITAL BUS B CONTROL 124 303/G 095 Y Y Y Y Y 20 VBDP-10/14/15- VITAL BUS STATUS CONIROL 124 303/G 095 Y Y Y Y Y SIP INDICATION PANEL B FOR VBDP-10/14/15 14 VBDP-11 EFIC VITAL BUS D CONIROL 124 303/G 095 Y Y Y Y Y 20 VBDP-11-SIP VITAL BUS STATUS CONTROL 124 303/G 095 Y Y Y Y Y. ~

INDICATION PANEL D FOR VBDP-Il 14 VBDP-12 120 VOLT REGULATED CONTROL 108 301/H 095 Y Y Y Y Y DISTRIBUTION PANEL 14 VBDP-13 120 VOLT REGULATED CONIROL 108 301/H 095 Y Y Y Y Y DISTRIBUTION PANEL 14 VBDP-14 120 VOLT REGULATED CONTROL 108 302/I 095 Y Y Y Y Y DISTRIBUTION PANEL 14 VBDP-15 120 VOLT REGULATED CONIROL 108 302/I 095 Y Y Y Y Y DISTRIBUTION PANEL 16 VBIT-1A DUAL INPUTINVERTER 3A CONTROL 108 301/G 095 Y Y Y N N 16 VBIT-1B DUAL INPUT INVERTER 3B CONTROL 108 302/H 095 Y Y Y Y Y 16 VBIT-IC DUAL INPUTINVERTER 3C CONIROL 108 302/H 095 Y Y Y Y Y 16 VBIT-ID DUAL INPUTINVERTER 3D CONTROL 108 302/H 095 Y Y Y Y Y 16 VBIT-lE DUAL INPUT INVERTER 3E CONIROL 108 302/H 095 Y Y Y Y Y Appendix C 54

M (v) (w. .

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAP CAV ANCH INTER EQUIP L RC EL OK OK OK OK OK 4 VBTR-1A CONSTANT VOLTAGE CONIROL 124 302/H 095 Y Y Y Y Y TRANSFORhER A 4 VBTR-1B CONSTANT VOLTAGE CONTROL 124 302/H 095 Y Y Y Y Y TRANSFORMER B 4 VBTR-2E 480/120V REDUNDANT CONTROL 108 302/H 095 Y Y Y Y Y-POWER SUPPLY TRANSFORhER 3E 4 VBTR-3E REDUNDANTPOWERSUPPLY CON 110L 108 302/H 095 Y Y Y Y Y SOLATRON 3E 4 VBTR-4A REGULATING CONTROL 124 303/G 095 Y Y Y Y Y TRANSFORNER A 4 VBTR-4B REGULATING CONTROL 124 303/G 095 Y Y Y Y Y TRANSFORNER B 4 VBTR-4C REGULATING CONTROL 124 303/G 095 Y Y Y Y Y TRANSFORhER C 4 VBTR-4D REGULATING CONTROL 124 303/G . 095 Y Y Y Y Y TRANSFORhER D 2 VBXS-IA VITAL BUS TRANSFER CONTROL 108 302/1 095 Y Y Y Y Y SWITCH A 2 VBXS-1B VITAL BUS TRANSFER CONTROL 108 302/H 095 Y N Y Y N SWITCH B 2 VBXS-lC VITAL BUS TRANSFER CONIROL 108 301/H 095 Y N Y Y N SWITCH C 2 VBXS-ID VITAL BUS TRANSFER CONIROL 108 302/1 095 Y N Y Y N SWTTCH D 2 VBXS-1E hiANUAL TRANSFER SWITCH CONTROL 108 302/1 095 Y Y Y Y Y 20 VBXS-2A AtTTO TRANSFER SWITCH CONIROL 145 302/H 095 Y Y Y Y Y FOR NNI Appendix C 55

CLASS ID NO EQUIP DESCRIPTION BLDG E ROOM BASE CAF CAV ANCH INTER EQUIP l L RC .EL OK OK OK OK OK i 20 VBXS-2B AUTOTRANSFER SWTTCH CONIROL 145 302/H 095 Y Y Y Y Y FORICS 2 VBXS-3A EFIC VITAL BUS TRANSFER CONIROL 108 301/1 095 Y Y Y Y Y-SWTTCH A 2 VBXS-3B EFIC VITAL BUS TRANSFER CONTROL 108 302/G 095 Y N Y Y N-SWITCH B 2 VBXS-3C EFIC VITAL BUS TRANSFER CONIROL 108 301/1 095 Y Y Y Y Y SWITCH C 2 VBXS-3D EFIC VITAL BUS TRANSFER CON 1ROL 108 302/G 095 Y N Y Y N SWITCH D 21 WDHE-1 REACTOR COOLANT DRAIN REACTOR 095 095 Y N/A N/A N/A Y TANK COOLER 12 WDP-1A WASTE GAS COMPRESSOR A AUXILIARY 095 303/O 095 Y Y Y Y Y 12 WDP-1B WASTE GAS COMPRESSOR B AUXILIARY 095 303/P 095 Y Y Y Y Y 21 WDT-1A WASTE GAS DECAY TANK 1 A AUXILIARY 095 302/Q 095 Y 21 WDT-1B WASTE GAS DECAY TANK IB AUXILIARY 095 302/O 095 Y 21 WDT-lC WASTE GAS DECAY TANK IC AUXILIARY 095 303/R 095 Y 21 WDT-3A RC BLEED TANK 3A AUXILIARY 095 303/Q 095 Y N N/A N/A N 21 WDT-3B RC BLEED TANK 3B AUXILIARY 095 304B/Q 095 Y N N/A N/A N 21 WDT-3C RC BLEED TANK 3C AUXILIARY 095 305/Q 095 Y N N/A N/A N 21 WDT-5 REACTOR COOLANT DRAIN REACTOR 095 NW OF D-RING 095 Y Y U Y U TANK Appendix C 56

O O O CLASS D NO EQUIP DESCRIPTION CLDG ROOM MASE CAF CAV ANCH INTER EQUIP RC EL ' OK OK OK OK OK CERTIFICATION: CERTIFICATION:

All the information contained on this Screening Verification Dats The inforunation provided to the Seisanic C ;--il;y Eagnacers Sheet (SVDS) is, to the best of our knowledge and belief, cornet and regarding systems and operations of the equipment contained on this accurate. "All Information" includes each entry and conclusion SVDS is, to the best of our knowledge and behef, cornet and (whether vertified to be seismically adequate or not).

Appmed: (One signatuit of Systems or Operations Engineer is Approved (Signatures of all Seismic Capability Engineers on the required if the Seisanic Capabehty Engineers deena it Seismic Review Team (SRT) are required: there should be necessary.)

at least two on the SRT. All signatories should agree with all of the entries and conclusions. One signatory should be a licensed professional engineer.)

Signatures below att for the specific items rniewed by each of the signatories. Documentation of the SRT members for each specific item is prmided on the SEWS for the item. All SEWS have been signed by at least two SCEs, at least one of which is a Registered Professional Engineer.

PADL 5 M(TH QOL \2/t 9/CIS Print or type name Signature Date Print or type name Signature Date C6LEW R47l n /2 0 PF Print or type name Signature Date Print or type name Signature Date HAWf 3DHM '

j, 12Rr/9r Print or type manic sh Date Print or type name Signature Date

%d # di absk Print or type name Signature [ Date Print or type name Signature Date Print or type name Signature Date Print or type name Signature Date Appendix C 57

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l FLORIDA POWER CORPORATION ^ '

l CRYSTAL RIVER UNIT 3 i

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! APPENDIX D l THIRD PARTY AUDIT REPORT 1

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VECTRA.

October 27,1995 2

0092-00239.000-LTR001 Mr. C. Glenn Pugh (MAC : NAIE) .

' Florida Power Corporation

• Crystal River Energy Complex 15760 W. Power Line St.

Crystal River, FL 34428-6708 e

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Subject:

' PEER Review of Crystal River Unit 3 A-46 Program l-4 Dear Mr. Pugh!

, s This letter is intended to document the results of the A-46 reviews and walkdowns that I i conducted the week of September 11 at Crystal River.

Attachment A details the observations which I had discussed with you and the walkdown team during the exit meeting on September 15,1995.

As was discussed, the implementation of your plant specific procedure is being performed in a thorough and competent manner. The results and findings from the completed effort appear

[ to be reasonable and are consistent with expectations for a plant of CR3's vintage. The I

!. equipment and raceway distributed systems were found to be rugged owing to conservative

original design and upgrades which have been implemented over the life of the plant. With very few exceptions, the equipment observed was found to be well maintained and having g good material conditions; while some improvements for seismic considerations are required, the general housekeeping practices appear to be well controlled and effective.

If you have any questions or comments, please do not hesitate to contact me at (508) 647-1050.

Very truly yours,

[Mf$%J Charbel M. Abou-Jaoude, P.E.

GA _

Project Manager

- Attachments cc: ;Mr. Anthony Petrowsky Mr. Al Friend VECTRATechnologies 'nc 12 Michigan Drive Natick. MA 01760 Tet (508)6471000 FaE(508)6474294 lb

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Attrchmtnt A to Letter 0092-00239.000-LTR001 l i

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ygg Seismic Peer Review of the CR3 A-46 Program l

This attachment provides a summary of the seismic reviews of the Crystal River A-46 program. An overview of the review process is first presented, general observations and comments are then discussed.

The Crystal River plant specific procedure and the supporting technical basis report were first reviewed. An electronic database containing a listing of all equipment within the A-46 scope l was then obtained and manipulated to generate a spreadsheet to serve for documenting the peer reviewer's field observations; the format used is similar to the GIP Screening Verification  !

Data Sheets (SVDS) with an additional field for walkdown notes. A two day plant walk-  !

through of all accessible areas excluding containment and high-rad areas was then  !

conducted. The equipment that was covered is close to 40% of the total A-46 items. The l

inspections focused on assessing the seismic capability of equipment by reviewing the  ;

component design characteristics, anchorages, and potentia! interactions; representative  !

electrical items were reviewed using the assistance of plant maintenance personnel to gain?

access to the intemals and anchorages of cabinets. The areas covered included:

- Mechanical and Electrical components in the Aux. Bldg. between elevations 75' and 119'

- Electrical control and distribution equipment in the Control Bldg. between elev 108' i f and 145'

- Diesel Generator Sets, Turbine Bldg areas, and Tanks in the Yard Review of the above areas provided a broad sampling of each of the 20 SQUG classes, tanks and heat exchangers, and electrical raceways.

Subsequent to the plant visit, the peer reviewer compared his field observations with those of the seismic review team as documented on completed SEWS. Also data packages which contained supporting drawings were sampled.

Based on the above reviews, the seismic assessments at CRS are being conducted in a thorough and competent fashion. The findings are consistent witn the observations and expectations of the peer reviewer. The majority of the conditions identified by the reviewer as requiring further evaluations or upgrades had been previously noted by the SRT. The completed SEWS were adequately documented and the appropriate judgment and conclusions were recorded in accordance with the CR3 PSP. The equipment list was very comprehensive and appears to include more equipment than is typically used or relied upon at other PWR's for the A-46 shutdown. The equipment reviewed was typically rugged and reasonably well anchored. A few instances for electrical cabinets were noted with irregular anchorage installations or configurations; however, in most cases the top entry conduit I configurations or existing anchorage pattern would be sufficient to support the low inertial demand levels. The cable tray supports were typically angle iron trapeze frames or rod hung in the turbine area; the conduit supports were unistrut frames or rod hung trapezes.

O Page A-1 October 27,1995

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V Attachment A to Lattgr 0092-00239.000-LTR001 Seismic Peer Review of the CR3 A-46 Program VECTRA The distributed systems are generally well designed and very rugged for a low seismicity site.

A number of upgrades to equipment and distributed systems were observed; these have been performed over the life of the plant and have resulted in increased margins. Good housekeeping and material conditions were observed throughout the plant, the only visible corrosion issue that was noted was for the D.G. fuel transfer pumps.

Based on the peer reviewers experience, plant walkdowns are the most valuable element of any seismic assessment program; very often, extensive documentation and analytical efforts only tend to reconfirm the field judgment. Given the low seismicity for a Florida plant, the streamlined GlP based program being implemented is appropriate and will enable FPC to capture any seismic vulnerabilities at CR3.

OBSERVATIONS / COMMENTS.

u General comments on the technical basis document are first discussed. These are primarily intended as suggestions to reinforce the FPC arguments and position. Then observations related to field inspections are presented. Allissues summarized here have been identified

. during the site visit and were discussed with the SRT.

- Technical Basis Reoort:

Seismic Demand The key argument for the streamlined or prescreening approach developed by FPC is the one relative to low seismicity and low demand (in Structure Spectra). The point being made in Appendix A gets a bit diluted when the emphasis is shifting to address the few components located at elevation 162' of the Aux. Bldg. Instead,

, the thrust should be on establishing a large comfortable margin between realistic in-l structure spectra and the SSRAP reference spectrum. If one fails to prove this i point and the conclusion is that the in-structure response spectra is only enveloped by the reference spectrum, then indirectly it could be inferred that the demand is so high that the full GIP requirements now need to be addressed.

l On page A-4 first paragraph line 7 (..., or a total amplification of about 1.3): the total amplification is more likely equal to 2.5 x 1.4 (not 0.53) = 3.5.

! Some of the arguments being presented in the introduction in relation to the 0.1g j could be 'made by using the Mercalli intensity to substantiate some of the qualitative i

statements made (0.1g corresponds to MM VI where as the SQUG data base sites l had a MM Vill or IX).

in generalit would be preferable to present the arguments in a positive light. For

i. example, on page 4 the discussion about the 8Hz rule could be stated as an area

where the GlP rule was generically satisfied instead of stating "CR3 PSP does not l have to explicitly address the GIP issue., ",

I- Page A-2 October 27,1995

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Attachmsnt A to Lettsr 0092-00239.000-LTR001 4

Seismic Peer Review of the CR3 A-46 Program VECTRA Raceways Much of the discussion in this section and in Appendix B is aimed at addressing the GlP 3DL screening criteria for nonductile support configurations. Here again the arguments are presented with the optics of justifying a deviation from the GIP analytical screening guidelines. While the GIP provides this 3DL check as one screening option, further analytical steps are available for evaluation of configurations that do not satisfy this simple check. It is probably just as easy to demonstrate that the CR3 configurations which do not screen to the 3DL check may very well meet other GIP analytical screening options. Most of these options do factor in the actual demand level and allow for relief based on the margin between the site SSE and the bounding spectrum.

Finally for the inclusion rules, on page B-9 a statement is made that the CR3 safety-related raceways do not use beam clamps. During the field walk through a conduit support detail which uses a friction clamp was identified at various locations. In all I cases observed, it was judged that enough redundancy existed in the conduit support configuration that reliance on the friction clamp was not necessary. This detail should be explicitly addressed preferably based on field inspections. ,

I O Relays A very detailed argument is presented in Appendix C to justify relief in this area.

The most defendable position is the performance of a screening for bad actors, and quantification of the low probability for loss of offsite power (see Finding 5 page C-5). From various PRA studies, a lower bound median value for damage to switchyards is 0.3g; therefore tnere is a high confidence of a low probability of a loss of offsite power below 0.1g. Without the loss of offsite power the operators are offered considerably more flexibility in shut-down/ manual options, hence reducing the importance of any relay chatter consequences.

Anchorage The CR3 position could be easily reinforced by performing a couple bounding anchorage evaluations. This would serve as a vehicle to support the SRT's judgments and illustrates the low level of demand on the CR3 installations.

- Field Reviews The walRdowns observed were being conducted in a thorough and well organized fashion. The SRT has exercised appropriate judgments and documented the walkdown results in accordance with the CR3 PSP.

Only a few minor comments are made here oased on the comparisons between the peer reviewer's walkdown observations and the SRT's SEWS. Cases where the peer reviewer's conclusions were different than the SRT's are presented based on O , the component ID.

Page A-3 October 27,1995 0

V Attachm:nt A to Lettsr 0092-00239.000-LTR001 Seismic Peer Review of the CR3 A-46 Program .

VECTRA DPBA-18: These newly installed station batteries have instances where a 3/8" gap exists between the batteries and the side rails; this was not identified in the SEWS.

Also based on the review of the data package, there is no evidence of the cell weight; the SRT concluded that the battery weight was within the GIP limits. A positive confirmation that the weight is less than 450 lbs. is required. These newer vintage batteries are large and may be more than 450 lbs. Note however, that the battery racks were tracked as outliers because of an anchorage concern.

AHF-54A: EFIC Rooms Cooling, these fan coil units are being tracked as equipment class 9. SQUG class 10 is more appropriate for these components (same applies to AHF-54B, AHF-17A&B).

DCP-1B: A long run of piping connected to this pump has an axial pipe support which uses a pipe clamp without any axiallugs that could be visually confirmed from a distance. This needs further review.

Finally for the beam clamps see the earlier discussion on raceways.

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