ML20050K923
| ML20050K923 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 04/09/1982 |
| From: | Flanagan D HUNTON & WILLIAMS, LONG ISLAND LIGHTING CO. |
| To: | SUFFOLK COUNTY, NY |
| Shared Package | |
| ML20050K631 | List: |
| References | |
| ISSUANCES-OL, NUDOCS 8204140240 | |
| Download: ML20050K923 (120) | |
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'02 EC 12 mi 7 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )
)
LONG ISLAND LIGHTING COMPANY ) Docket No. 50-322 (OL)
)
(Shoreham Nuclear Power Station, ) Unit 1) ) LILCO'S FURTHER RESPONSE TO SUFFOLK COUNTY INTERROGATORIES On April 1, 1982, Suffolk County filed "Suffolk County Motion to Compel Answers to Interrogatories." Pursuant to an agreement between counsel, LILCO agreed to answer modified interrogatories, or to expand its previous answers. This docu-ment contains LILCO's further response to Suffolk County inter-rogatories. Affidavits are attached. SC Contention 1 Interrogatory 18 Identify all indicators related to the RHR, RBCLCW and service water systems at remote equipment locations to be used by operators in the field assisting in remote shutdown, and identify the range displayed by each such indicator. K O$$0Q PDR
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Response
LILCO reiterates its earlier answer. Specifically, with regard to the RHR, service water and RBCLCW systems, no instru-ments or other indicators, other than those on the RSP, are needed to shut down the plant under the RSP design basis. Under the design basis for the RSP, there are no procedures -- operating or emergency -- which call for the use of operators in the field to assist the remote shutdown operator by reading instruments or other indicators related to the RHR, service water or RBCLCW systems at remote locations. SC Contention 3 Interrogatory 29 With respect to each response to Interrogatory No. 28, describe how the degree of accuracy was determined and identify all documents concerning such determination. Response. See Attachment 1. SC Contention 4 Interrogatory 35 Does LILCO intend to evaluate, or has LILCO in fact evalu-ated, any problems identified at other General Electric BWR Mark II plants (U.S. or Caorso) to determine their relevance to Shoreham and to determine whether Shoreham's pre-operational testing program for water hammer should be modified? If yes, identify all documents which evidence or concern this matter. f I
1
Response
No, but LILCO is considering such evaluations. SC Contention 13-15 Interrogatory 11 State how many LILCO QA/QC personnel will be present during each operating shift at Shoreham when the plant is in operation. Explain the basis for LILCO's selection of this number and outline their respective duties.
Response
LILCO Operational Quality Assurance will be staffed with an Operating QA Engineer, QA Engineer, QC Engineer and 5 QC Inspectors during the regular work day. The selection of this number of LILCO QA/QC personnel was determined from surveying QA/QC manpower at operating single unit Boiling Water Reactors. As workload requires (i.e., during scheduled, major main-tenance overhauls or scheduled fuel outages) OQA personnel will work scheduled overtime as necessary. During any emergency work at the station, OQA personnel will be on call to provide QA/QC coverage. It is expected that during station refueling outages, OQA may require outside QA/QC contractor assistance. Outside QA/QC contractor personnel will be qualified and certi-fied to the LILCO QA program. l The respective duties of the Operating QA Engineer, QA Engineer, QC Engineer and QC Inspectors are described in detail in the following documents:
3 LILCO Quality Assurance Manual SP #12.003.01 Personnel Qualifications and Responsibilities QAP-S-01.1 Operational Quality Assurance Organization FSAR, Section 13. These documents have been made available previously for the County's review. SC Contention 13-15 Interrogatory 12 Describe the QA/QC support to Shoreham operations which is now being provided, or will be provided in the future, by gen-eral office personnel employed by LILCO.
Response
The LILCO Quality Assurance Department, located off-site, will be available to provide QA/QC support to the Shoreham op-erations. The current authorized personnel strength of this department includes 17 professional personnel and 3 techni-cal / clerical personnel. Services provided by this department include: Maintaining the QA Program current with on-going l events and regulations. Performing Procurement QA/QC such as review of LILCO procurement documents; evaluation of potential sup-pliers; and survey, audit and inspection of suppliers and their facilities. 1 i Review off-site organizations' procedures and audit of their activities. Review of OQA procedures and audit of OQA Section and certain station activities.
3 Administration of the LILCO NDE program including training and certification of NDE personnel. Participation in the LILCO welding program. SC Contention 13-15 Interrogatory 22 Please identify "those applicable elements of the QA Program in which quality-based related activities are more intensive and impacting upon daily operation" (FSAR Section 17.2) which shall be audited at least annually (i.e., what are the " applicable elements" and what are the " quality-related activities" referred to).
Response
The QA Program is applied to the safety-related struc-tures, systems and components listed in FSAR Table 3.2.1-1. Activities affecting these safety-related structures are con-sidered quality-related. The activities considered more inten-sive and impacting upon daily operation include operation, maintenance, modification, repair, refueling, inspection and testing of safety-related structures, systems and components. The QA Program is designed to assure that these quality-related activities are accomplished in accordance with the criteria of I 10 CFR 50, Appendix B. l Respectfully submitted, LONG ISLAND LIGHTING COMPANY W. O@ % Taylor Reveley, III % Anthony F. Earley, Jr. Daniel O. Flanagan Hunton & Williams , 707 East Main Street l Richmond, Virginia 23212 l 1 1 m )
, l ATTACHMENT 1 RPV LEVEL INSTRUMENTS Mfg. Pub-lished Manu-S&W Mark # GE# Loop Name Range Accuracy facturer B21-LIT *0 0 4 A B21-N026A Wide Range -150/o/+60" See Note Barton 1 Below B21-XR-004A B21-R623A Wide Range -150/o/+60" 0.5% Bailey B21-LIT *004B B21-N026B Wide Range -150/o/+60" See Note Barton 1 Below C61-LI-004 C61-R010 Reactor -150/o/+60" 1.5% GE Vessel Wide Range B21-LIT
- 004C B21-N026C Wide Range -150/o/+60" See Note Barton 1 Below B21-XR-004B B21-R623B Wide Range -150/o/+60" 0.5% Bailey B21-LIT *004D B21-N026D Wide Range -150/o/+60" See Note Barton 1 Below B21-LI-004D B21-R604 Reactor -150/o/+60" 1% Weston Vessel Wide Range B21-LIT *007A B21-N037A Fuel Zone -150/o/+60" See Note Barton 1 Below B21-LR-007 B21-R615 Fuel Zone -150/o/+50" 0.5% Bailey B21-LIT *007B B21-N037B Fuel Zone -150/o/+60" See Note Barton 1
B21-LI-007 B21-R610 Fuel Zone -150/o/+50" 1% Weston B21-LT-005 B21-N027 Upset Range 0-400" I 0.25% of Rosemount Calib. Span B21-LI-005 B21-R605 Upset Range 0-400" 1% Weston NOTE 1: Accuracy is I .5% I Outside 20% (Full Scale Differential Pressure) of the Switch Point I .5% 2 Within 20% (Full Scale Differential Pressure) of the Switch Point
Mfg. Pub-lished Manu-S&W Mark # GE# Loop Name Range Accuracy facturer C32-LT-008A C32-N004A Narrow Range 0 - 60" I 0.4% Rosemount C32-XR-006 C32-R608 Narrow Range 0 - 60" I 0.5% Bailey C32-LT-008B C32-N004B Narrow Range 0 - 60" 0.4% Rosemount C32-LI-008B C32-R606B Narrow Range 0 - 60" 1% Weston C32-XR-006 C32-R608 Narrow Range 0 - 60" I 0.5% Bailey C32-LT-008C C32-N004C Narrow Range 0 - 60" I 0,4% Rosemount C32-LI-008C C32-R606C Narrow Range 0 - 60" 1% Weston C32-PDT-005 C32-N017 Wide Range 0 - 180" .0;4% Rosemount C32-XR-006 C32-R608 Wide Range 0 - 180" O.5% Bailey i l
. UNITED STATES OF AMEitICA
;- NUCLEAR REGULATOEY COMMISSION y Before 'the Atomic Safety and Licensing Board In the Mattar of )
)
. LONG ISLAND LIGHTING COMPANY ) Docket No. 50-322
)
(shorehan Nuclear Power Station. ) Unit 1) )
,. AFFIDAVIT OF__ JOHN _D.__ LYNCH .;: i John D. Lynch, being duly sworn, states as follows:
4 1. I an a Licensing Engineer with the Nuclear Operations 2 Support Department for the Long Island Lighting Company for
.g. preparation of material for the Shorehan Operating License.
- 2. Long Island Lighting Company's further response to g SC's set of Interrogatories (Contention 1, ques. 18 contentions 13-15, ques. II, 12, 22) were prepared under my i information, knowledge and belief, the answers contained in those responses are true and correct.
, /
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hn D. Lynsi '
. Subscribed and sworn to before se this F day of April, 1982.
Y~ Notary Public b> b : > t.:..L:: ::~a. : N-- " ' ' ' ' c' t : um t.. . : ..:.a Ny Commission Espires: 9/ doff 4 C' 4 ' # - -' ' ' I ' '"J fdl
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\ ..- , UNI'f2D STATF1, Ow AMERICA NUCLEAR REGULATORY COMMTSSION Before the Atomic Safety and Licensing Board In the Matter of )
) ,
LONG ISLAND LIORTING COMPANY ) Docket No. 50-322 '
)
(Shoreham Nuclear Power Station. ) Unit 1) ) AWPTDAVIT OF MICHAEL L. SANDE Michael L. Sande, being duly sworn, states an follows:
- 1. I am an Instrumentation and Controls Engineer for the _
Long Island Lighting Company with the Power Engineering Department. I have been anz$5ned to the Nuclear Ooerations Support Department - for preparation of material for the Shoreham Operating License.
- 2. The *urther Response of Long Island Lighting Company to SC's March 5,1982 Request for Production of Documents (31) and i
SC's March 5,1982 Interrogatories (29 and 35) were prepared under my supervision and direction. To the best of my information, knowledge and belief, the answers contained in those responses are true and correct.
._ Y-Mibhael L. Bande W.
Subscribed and sworn to before me this 6th day of April,1982 , wbn $$a Notary Public
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3 t HUNTON & WILLIAMS 707 East MAIN sTRCCT P.O. Box 1535 e e 6 e evikoiwo RIcarwoxn, VIMOINIA 2 0 212 seio ac esas sVLvaNi A AVE NU C, N. W. p.o.somaos e o.somisaso matteow, montw camouma areoa * * * * ' " #0" '" TC L t p H O N E a04-788-8200 eie-ea e . e s ti son-ass eas'o' C' # romer vinoeneA eAnn towen
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nomroks, vinoews A assie so4-eas.esos centet oiA6 wo eos ree-April 9, 1982 Stephen B. Latham, Esq. Twomey, Latham & Schmitt P. O. Box 398 Riverhead, New York 11901
Dear Steve:
! By this letter, I transmit to you a copy of SNRC-526 (December 31, 1981), which was referenced in "LILCO's Response to SOC's Third Set of Interrogatories and Request for Production of Documents to Long Island Lighting Company," of April 2, 1982. SNRC-248 (and not SNRC-148 as our earlier re-sponse indicated) deals with the preservice inspection program.
SNRC-248 and subsequent revisions to the plan have been incor-porated into a two volume binder set, "Shoreham Nuclear Power Station - Unit 1, Preservice Inspection Program Plan." This set will be made available for SOC's review at a convenient time and location. In addition, in the " Response of Long Island Lighting Company to SOC's March 1, 1982 Interrogatories and Request for Production of Documents," reference was made to two other reports, both dealing with SOC Contention 19(a): l l l
I O l li t:N T O N & WILLI AMS Stephen B. Latham, Esq. Page 2 April 9, 1982
- 1. "Preservice Inspection of the Shoreham Nuclear Power Station Unit 1 Reactor Pressure Vessel," by Nuclear Energy Services, Inc.
- 2. " Reactor Pressure Vessel Inspection" by Reinhart &
Associates, Inc. The reports have not been finalized, but the draft versions are enclosed. Sincerely, aLaQ O h u,sq M Daniel O. Flanagan 271/447 cc: Lawrence Brenner, Esq. Dr. Peter A. Morris Dr. James H. Carpenter Service List t
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LONG ISLAND LIGHT!NG COM PANY
, [h8hf SHOREHAM NUCLEAR POWER STATION P.O. SOX 618. .JORTM COUNTRY ROAD . WADING RIVER. N.Y.11792 December 31, 1980 SNRC-526 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Reactor Building Separation Analysis Ref. SNRC-471, April 16, 1980 and SNRC-493, August 14, 1980 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322
Dear Mr. Denton:
As discussed in the referenced letters, enclosed herewith are six (6) copies of the Shoreham preliminary REACTOR BUILDING SEPARATION ANALYSIS REPORT dated December 22, 1980. This submittal provides a description of the analysis performed and includes the analysis results for the Reactor Building primary containment drywell area and elevation 8' of the secondary containment. Analyses results covering the remaining levels within the secondary containment are in
-the final stages of completion and will be submitted during a forthcoming review meeting with your Staff. Your pre-review of this material should provide for a more meaningful discussion at this meeting.
This analysis demonstrates that sufficient separation exists between redundant systems and components within the Reactor Building. Thus the capability to safely shut down the station, in the event of a postulated fire.which results in the disability of all cables and raceways in an entire designated area, is maintained. This analysis will be an ongoing effort which will terminate with the completion of the installation of all Class IE cables and associated equipment. At that time, an engineering and construction "as-built" review will be performed to reaffirm the analysis results. , Very truly yours, h bec: Dist. List #14 O J. P. Novarro, Eng. File /SR2...A21.010 Y Project Manager gNp Shoreham Nuclear Power Station Enclosures re sess cc: J. Higcins JPM/cc R. T. Carlson
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, 11600.02-158 a 12/22/80 058 (PRELIMINARY) 1.8 REACTOR BUILDING 1.10 SEPARATION ANALYSIS REPORT 1.11 SHOREHAM NUCLEAR POWER STATION - UNIT 1 1.13 LONG ISLAND LIGHTING COMPANY 1.14 l
I l Prepared by STONE & WEBSTER ENGINEERING CORPORATION
/
. 1160 0. 02-158 b 12/22/80 058 TABLE OF CONTENTS 1.10 Section Title Page 1.13 1 PURPOSE. . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.15 2 GENERAL METHOD OF ANALYSIS . . . . . . . . . . . . . . . . 1 1.17 3 ASSUMPTIONS. . . . . . . . . . . . . . . . . . . . . . . . 1 1.19 4 SPECIFIC METHODS OF ANALYSIS . . . . . . . . . . . . . . . 2 1.21 4.1 AFFECTED AREAS . . . . . . . . . . . . . . . . . . . . . 2 1.23 4.1.1 Primary Containment. . . . . . . .. . . . . . . . . . 2 1.25 4.1.2 Secondary Containment. . . . . . . . . . . . . . . . . 2 1.26 4.2 SHUTDOWN MODEL . . . . . . . . .'. .. . . . . . . . . . 2 1.28 4.3 SHUTDOWN EQUIPMENT . . . . . . . . . . . . . . . . . . . 3 1.30 4.4 DEVELOPMENT OF SHUTDOWN EQUIPMENT BY AREA. . . . . . . . 7 1.32 5 RESULTS AND RECOMMENDATIONS. . . . . . . . . . . . . . . . 8 1.34 6 CONCLUSIONS. . . . . . . . . .. . . . . . . . . . . . . . 9 1.36 7 UPDATE OF REPORT . . . . . . . . . . .. . . . . . . . . . 9 1.38 APPENDIX A - Separation Analysis Results - Primary 1.40 Containment 1.41 APPENDIX B - Separation Analysis Results - Secondary 1.42 Containment 1.43 e
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l 11600.02-158c 12/04/80 162 LIST OF TABLES 1.10 Table Title 1.13 1 1.1-1 Primary Containment Areas 1.16 1 1.2-1 Secondary Containment Areas 1.17 1 4-1 Systems with Class IE Cables 1.18 1 4-2 Shutdown Equipment List 1.19 LIST OF FIGURES 1.22 Fiqure Title 1.25 1 1.1-1 Arrangement of Primary Containment Areas 1.28 1 1.2-1 Arrangement of Secondary Containment Areas 1.29 4.2-1A Shutdown }!odel - (SH1) 1.30 1 2-1B Shutdown Model (SH2) 1.31 1 2-1C Shutdown Model (SH3) 1.32 1 4- di Development of Shutdown Equignent vs. Area Lists 1.33~ 11
4 ( 11600.02-158d 12/24/80 051 1 PURPOSE 1.13 This analysis is made to demonstrate that sufficient separation 1.14 exists between redundant systems and components n_ecessary for 1.15 shutdown such that a postulated event causing the disability of all cables and raceways in an entire designated area will not 1.16 Brevent a plant safe shutdown. 1.17 2 GENERAL METHOD OF ANALYSIS 1.19 The primary and secondary containments are divided into "Affected 1.20 Ar eas . " All cables and raceways in each "Affected Area" are 1.22 assumed to be disabled such as to render them unavailable for use in ghutdown. A determination is then made whether shutdown can 1.25 be achieved using the remaining shutdown equipment of other unaffected areas. The areas are chosen conservatively large and 1.27 the disabling event is fire. Loss of offsite power is assumed 1.28 concurrent with the postulated event. 3 ASSUMPTIONS 1.30 The following are the assumptions and design bases for the 1.31 separation analysis:
- 1. It is assumed that: 1.33
- a. The reactor is operating at 100 percent power when 1.36 the postulated event occurs.
- b. Only onsite power is available in achieving safe 1.37 shutdown.
- c. The reactor is isolated from the main condenser. 1.38
- d. There is an automatic scram (or manual at the 1.39
- direction of the shif t supervisor) to bring the plant to hot shutdown. 1.40
- 2. As presented in the NRC review reminder (1), it is 1.42 assumed that there is a 72 hour period in which to achieve cold shutdown. During this three day period, 1.44 credit may be taken for manual system operation as well as for reasonable repairs, etc.
l l 6 (1) Nuclear Regulatory Commission. " Review Reminderd from V. Benaroya to Auxilary System Branch Staff Members, August 8, 1978. 1 l 1
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11600.02-158d 12/24/80 051 i SPECIFIC METHODS OF ANALYSIS 1.50 11 AFFECTED AREAS 1.51 In order to separate the primary and secondary containments into 1.52 _ conservative affected areas, overlapping segments are defined as 1.54 described below. 4.1.1 Primary Containment 1.56 For the primary containment drywell areas, 60 degree segments are 1.57 chosen. There is no vertical division within the structure. 2.1 C_aole and raceways in each segment are disabled and a 2.2 i determination made whether shutdown can be accomplished with the remaining equipment. Upon completion of the analysis of each 2.5 area, the procedure is repeated with new 60 degree segments which are rotated or indexed 30 degrees from the previously analyzed 2.6 segments. Thic overlap operation assures that no sensitive 2.7 interface boundaries exist. 1 F_igure 4.1.1-1 illustrates the arrangement of the primary 2.8 containment areas, and Table 4.1.1-1 describes the area 2.10 boundaries. 4.1.2 Secondary Containment 2.12 The method used for the secondary containment is the same as for 2.15 the primary containment except that 45 degree segments are used and are indexed by 22.5 degree increments. Because there are 2.16 , distinct floor levels within the secondary containment, vertical 2.17-boundaries are established for the s_econdary containment areas at l each floor elevation. . Figure 4.1.2-1 illustrates the arrangement of the secondary 2.18 containment areas, and Table 4.1.2-1 describes the area 2.19 boundaries. 4.2 SHUTDOWN MODEL 2.21 In order to make a determination that shutdown is achievable with 2.22 the cable and raceway in a given area disabled,.it is necessary 2.24 to develop a functional model for shutdown. This model is 2.25 illustrated in Figures 4.2--1A, 4.2-1B, and 4.2-1C. Paths to successful shutdown are shown in this model. All 2.27 systems, saf ety and nonsaf ety, which can contribute to plant shutdown are identified. All auxiliary systems, such as 2.28 ventilation, cooling water, control and instrumentation, as well as electrical power sources are included. In the analysis, 2.30 l however, credit is taken only for safety-related systems and I equipment. 2 m-,w,--mv--*-, - - - - -- . - . - - - - - , - , , , , , - - - - - - ..,-.=------,emw- e-w-ne --.-w u- r- m*'---w-T-'l.---=sw---w-aw -uwe --w-- -- --'
, e *', 11600.02-158d 12/24/80 051 4.3 SHUTDOWN EQUIPMENT 2.32 Based on the shutdown model and use of saf ety-related systems 2.33 only, the gelection of shutdown components is made as follows: 2.34 1 System B21 - suelear Boiler 2.36 The eleven ADS and saf ety-relief valves are required to 2.38 operate only manually. Automatic initiation is not 2.40 necessary and will not normally occur since no LOCA and therefore no high drywell Eressure is assumed which is 2.42 required for automatic initiation. ~The three head vent 2.43 valves MOV083, 084, and 085 are required to prevent blowdown of the reactor vessel into the primary 2.44 containment due to opening of two series valves. The SRV's may be utilized for a combination hot / cold 2.45 shutdown operation. With the vessel at high pressure, 2.46 the valves can provide sufficient pressure relieving capacity to enable the low head systems (LPCI and Core 2.47 Spray) to provide core inventory. With the vessel at 2.48 low pressure, the valves can provide extended core and/or suppression pool cooling by holding the valves 2.49 open, enabling the low head systems to provide a suppression pool / reactor vessel circulation path. Cooling would be provided directly or indirectly via 2.50 the RHR exchanger. The above modes are designated as 2.51 the RHR/CS/SRV flow path in the separation analysis. 1 Systam B31 - Reactor Recirculation System 2.53 The two pressure switches, PS023A and B, for automatic 2.55 RER system operation are needed.
- 3. System C41 - Standby Liquid Control 2.58 The safety-related portions of this system are required 3.3 in the event control rod insertion is not completed.
It is not desirable to have this system operate unless 3.5 it is actually required. 4 System C61 - Reactor Plant Remote Shutdown 3.8 The eight safety-related indicating transmitter 3.10 circuits for RHR main flow (FT001) , reactor vessel 3.11 pressure (PT00 6) , service water header pressure (PT011) , suppression pool temperature (TT022A and B) , 3.13 and level (LT026), and drywell pressure (PT012) and temperature (TT021) are required. 3.14 3 l l
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e l 11600.02-150d 12/24/80 051 , 5,. System E11 - Recidual Heat Removal 3.17 All safety-related components, except the following ten 3.19 valves, are required: The two flow to suppression pool 3.20 valves MOV042A and B are not required since the 3.22 normally closed upstream valves are protected. _The two 3.23 head spray isolation valves MOV053 and 054 are not required for shutdown since cable failure resulting in 3.24 both valves opening presents no problem since there is a check galve in series with these MOV's to prevent 3.25 reactor blowdown. The four heat exchanger vent valves 3.26 MOVOSSA and B and 056A and B are not required for 3.27 shutdown even during the steam condensing mode since cable failure resulting in o_pening of these valves will
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3.28 drain a one inch line from the heat exchanger opening to _the suppression pool, an acceptable event. The two 3.30 hydrogen recombiner subsystem valves MOV057A and B are not required for a non-LOCA condition and failure of 3.31 valve cabling will cause valves to open, an event which will not result in significant degrading of the RHR 3.32 cooling system. 6, . System E21 - Core Sprav 3.35 _All safety-related components are required, except the 3.37 two testable check v_alve bypass valves MOV081A and B, 3.38 which are not required during shutdown. If these 3.40 valves were to change state, there would be no adverse effect on system operation. Autcmatic initiation which 3.41 is based on reactor water level is also required. Initiation signals based on reactor primary containment 3.42 pressure are not required since _there should be no high 3.43 pressure condition without LOCA. Also, failure of the 3.44 high drywell pressure initiation signal will neither prevent injection nor cause the injection valves to 3.45 open prematurely because a reactor pressure permissive 3.46 in the control circuit of the injection valves will prevent valve opening on high reactor pressures. Ihis 3.48 permissive is considered a required component. l 7. System E41 - Hiah Pressure Coolant In-iection 3.51 i All safety-related components are required, except the 3.53 five items identified below. _One is the loop level 3.54 pump P-050 Which if lost will not adversely affect the 3.56 system since the time prior to initiation and between operating cycles ghort .enough to prevent significant 3.57 draindown of the ptanp discharge piping. Another item 3.58 ! is the inboard isolation valve bypass valve MOv047 which is not required for shutdown and will not affect 4.1 system operation in either the open or closed position. Also, the turbine exhaust vacuum breaker MOV049 is not 4.2 required and is used only after a LOCA. _ Lastly, the 4.3 condenser exhaust vacuum breaker PCV144 and steamline 4 l
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11600.02-158d 12/24/80 051 trap b_ypass valve LCV091 are not required for shutdown 4.4 and will, in fact, fall in the closed position on loss 4.5 of air due to loss of offsite power. Assuming 4.6 availability of air, failure of the control circuit resulting in valve o_pening is not detrimental to system 4.7 , operation. Automatic initiation based on reactor water 4.8 I level is required. Initiation due to high drywell 4.9 pressure is not required since there should be no such 4.10 condition without LOCA. Also, fallure of drywell 4.11 pressure initiation signal will not prevent injection, and if premature injection occurs, it will not 4.12 adversely affect reactor operation. Instrumentation to 4.13 identify HPCI steamline break which can cause steamline isolation is required. 8_ . System E51 - Reactor Core Isolation Cooling 4.16 _All safety-related components are required, except 4.18 those five corresponding to the E41 System (P-0 51, 4.19 MOV047, MOV049, PCV144 and LCV091) and for the same reasons. Automatic initiation is also required. 4.20 9_ . System G33 - Reactor Water Cleanup 4.24 The corttainment isolation valves MOV033 and 034 are 4.26 required to be closed _to isolate the reactor from the 4.27 remainder of the RWCU System. This isolation is 4.29 necessary if standby liquid control system initiation is required.
- 20. System G41 - Fuel Pool Cooling and Cleanup 4.32' The two service water inlet valves, MOV032A and B, used 4.34 for ultimate cooling water c_onnection and the 4.35 corresponding valves in the service water system, are 4.37 required to be closed to prevent pumping service water to the spent fuel s_torage pool, an event which in time 4.38 could cause flooding in the reactor building.
- 11. System M43 - Fire Protection 4.41
_Only the safety-related portion of this system is 4.43 required to prevent .i_nadvertent shutdown of the 4.44 ventilation system or nonclosure of Cor dampers so that 4.46 the Cor is confined to a fire area.
- 12. System MSO - RBSVS and Control Room A-C Chilled Water 4.49 All safety-related components are required. 4.51 1
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11600.02-158d 12/24/80 051 !
- 13. System P41 - Service Water 4.55 All safety-related components are required except the 4.57 ,
two radiation monitoring system isolation valves 4.58 MOV102A and B which are not needed during a non-LOCA condition. In addition, a failure causing the valves 5.2 , to open will not result in unacceptable conditions. Automatic initiation is also required. 5.3
- 14. System P42 - Reactor Building Closed Loop Coolina Water 5.6 System Ihe three P-005A, B, and C RBLCLW circulating pumps and 5.8 the two heat exchanger inlet isolation valves MOV042A 5.9 and B are required to supply c_ooling to RHR pump seals. 5.11 Valves separating Category I from Category II piping 5.12 and Division I from Division II E ii P ng are not 5.13 required. gperation of selected components will be 5.14 manual and no automtic initiation is required.
- 15. System P50 - Compressed Air 5.17 Ihe MOV's and pressure switches used to supply and/or 5.19 1solate the' air to the SRV accumulators are required.
All other components are Category II. 5.21
- 16. Systems R22, 23, 24, 35, 42, 43 - Electrical Distri- 5.24 bution All Class 1E electrical distribution and 5.26 interconnecting cable is required.
- 17. System T46 - Standhv ventilation System 5.30 gnly the fourteen unit coolers in the reactor building 5.32 are required .t_o maintain the ambient temperature around 5.33 the components needed for shutdown. _ Manual operation 5.35 only is required; automatic initiation is not needed.
Ventilation equipment required for maintaining negative 5.36 pressure in the reactor building secondary containment 5.37 is not needed. The filtering equipment is not required 5.38 ,, since there is no LOCA/ release ot radiation.
- 18. System X41 - Miscellaneous Room HVAC 5.41 All safety-related ventilation components are required 5.43 in these miscellaneous areas.
- 19. System X60 - DieselK,enerator ventilation 5.47
_All safety-related ventilation components in the D/G 5.49 rooms are required. f 6 w- 5--~- ..m.- 7,w -- - ---,--w,w- ,-g-,..,e-.- ---g -- _,._.%,., _ - - - - - - - -
4
.t
]
11600.02-158d 12/24/80 051
- 20. System X61 - Control Room A-C 5.53 All safety-related components are required, except the 5.55 two air-operated valves AOV37A and B which isolate the 5.56 redundant portions of ducts that will remain intact, 5.58 assuming no seismic condition. These dampers will fail 6.1 closed on loss of offsite power.
u.4 DEVELOPMENT OF SHUTDOWN EQUIPMENT BY AREA 6.4 The development of shutdown equipment by affected area is 6.5 illustrated in the cchematic diagram Figure 4.4-1. The first step consists of developing a shutdown equipment list. 6.7 This is accomplished by using the shutdown model developed, cs 6.8 described in Section 4.2, and identifying all systems with 6.9 safety-related cable (Table 4.4-1) . These are then compared to 6.10 the model requirements as indicated in Section 4.3 to sort out the safety-related equipment for shutdown. The shutdown 6.13 equipment list is contained in Table 4.4-2. The second step is to incorporate the elementary diagram (ESK) 6.14 information on the shutdown equipnent list. Since a complete 6.15 equipment versus ESK list already exists within the computerized Electrical Cable. Schedule Information Eystem (ECSIS), the 6.16 shutdown equipment list is input to the computer, compared against the equipment versus ESK list, and sorted to get the 6.18 shutdown equipment versus ESK list. The third step is to identify the cables associated with each 6.19 piece of shutdown equipment. This is accomplished by comparing 6.20~ the shutdown equipment versus ESK list generated in the previous step with the cable versus ESK list in the ECSIS. 6.21 gaving identified, at t.his point, all shutdown equipment and its 6.22 associated cable, it remains to identify the cable in each area 6.23
- and compare to the shutdown equipment in order to identify the disabled equipment.
The fourth step is to compile lists of cable trays and conduit by 6.24 area, input to the computer, and compare against the cable versus 6.25 raceway list in the ECSIS thus creating the cable versus area lists. The fifth step is to compare the shutdown equipment versus cable 6.26 list from step three against the cable versus area lists from 6.27 step four to identify the shutdown equipment lost for each area. The final step is to compare the unaf fected shutdown equipment 6.28 l versus area lists against the shutdown nodel to determine the 6.29 ( impact on safe shutdown capability. 6.31 , 7
.c 11600.02-158d 12/24/80 051 5 RESULTS AND RECOMMENDATIONS 6.33 7.13 Appendices A and B present the results of the separation analysis 6.34 , 7.14 for the primary and secondary containment respectively. y 7.16 e 7.17 Tne results are presented for each area investigated in the 6.36 e following format: 7.19
- 1. Systems Impacted (Division I and Division II) -
A 6.38 , 7.20 listing of any system which computer analysis indicated d 7.21 had Associated shutdown cable or cables in the area of 6.39 intere st. 7.24
- 2. System Functions Disabled - All safety systems and 6.40 compopents previously identified as essential and e 7.25 listed in Iables 4.4-1 and 4.4-2 are evaluated for 6.42 e 7.26 their importance in achieving a safe shutdown. _Those 6.43 7.27 components whose failure would not necessarily cause a system function loss are reviewed and, where no impact u_pon safe shutdown exists, are so noted under Disabled 6.45 Function Evaluation below. As an example, in Section 6.46 008-07, Paragraphs 1 (B) and 1(C) identify unit cooler 6.47 1T46*UC002A as a disabled 1T46, Division I, component.
However, the loss of that cooler does not affect the 6.48 remaining Division I, cooler (1T46*UC003A) and Division I 1T46 RBSVS components which have the gapability or- 6.50 providing cooling for the Division I equipment utilized for safe shutdown and identified in Paragraph 4, 6.51 Shutdown Capability. l Where an event damages extensive equipment in one train 6.53 (Division I or II) , a statement such as "No credit taken for Division I system functions" is made, and the 6.54 remaining statements generally refer to disabled functions in other Divisions. In such a case, the 6.56 analysis has determined that no Division I system functions are required to achieve safe shutdown.
- 3. Disabled Function Evaluation - Identifies, at the 6.58 system level, the importance to safe shutdown of any function that may be lost as a result of the event. 7.1 4 Shutdown Capability -
Identifies whether redundant 7.2 means of providing necessary safe shutdown functions are gvailable (given the Disabled Functions in 3) and 7.3 generally describes an available procedure for safe shutdown. i 1 Further Action Recommended - Provides recommendations 7.4 for required modifications which will further improve existing glant shutdown capability. These 7.7 recommendations are not necessarily requisites to achieving shutdown but rather enhancements which would augment existing capabilities. 7.9 8
', ,4 11600.02-158f 12/22/80 058 .
TABLE 4.1.1-1 1.8 PRIMARY CONTAINMENT AREA BOUNDARIES 1.10 Primary Segment Boundary Overlap 1.13 Area From To Area From To 1.14 N1 0* 600 01 300 900 1.16 N2 600 1200 02 900 1500 1.17 N3 1200 1800 03 1500 2100 1.18 N4 1800 2400 04 210e 2700 1.19 N5 2400 3000 05 2700 3300 1.20 N6 3000 00 06 3300 300 1.21 I 1 of 1 l
11600.02-158g 12/24/80 056 TABLE 4.1.2-1 1.8 SECONDARY CONTAIN!1ENT AREA BOUNDARIES 1.10 Primarv Segment Boundary overlap 1.13 Area From To Area From To 1.14 N1 00 450 01 22.50 67.50 1.16 N2 450 900 02 67.50 112.50 1.17 N3 900 1350 03 112.50 157.50 1.18 N4 1350 1800 04 157.50 202.50 1.19 NS 1800 2250 05 202.50 247.50 1.20 N6 2250 2700 06 247.50 292.50 1.21 N7 2700 3150 07 292.50 337.50 1.22 N8 3150 00 08 337.50 22.50 1.23 t Elevation From To 1.25 l 008 008 040 1.27 040 040 063 1.28 063 063 078 1.29 078 078 112 1.30 l 112 112 150 1.31 150 150 - 1.32 i l Segments are Numbered Elevation - Area 1.34 l Example: 1.35 063-N6; Elevation 063 to 078 Area 2250 to 2700 1.36 See Figures 4.1.1-1 and 4.1 1.37 l l 1 of 1 . 1
e a V 11600.02-158 e 12/22/80 058 TABLE 4.4-1 1.8 ALL SYSTEMS WITH CLASS IE CABLES 1.10 SHOREHAM NUCLEAR POWER STATION 1.11 LONG ISLAND LIGHTING COMPANY 1.12 System 1.15 No. Description 1.16 B 1.18
.B21 Nuclear Boiler 1.19
.B31 Reactor Recirculation 1.20 C 1.22 C11 Control Rod Drive Hydraulic 1.23 Control 1.24
.C41 Standby Liquid Control 1.25 C51 Neutron Monitoring 1.26
.C61 Reactor Plant Remote Shutdown 1.27 C71 Reactor Protection 1.28 D 1.30 D11 Process Radiation Monitoring 1.31 D21 Area Radiation Monitoring 1.32 E 1.44
.E11 Residual Heat Removal 1.45
.E21 Core Spray 1.46
.E41 High Pressure Coolant Injection 1.47 E32 MSIV Leakage Control System 1.48
.E51 Reactor Core Isolation Cooling 1.49 G 1.51
- G11 Radwaste 1.52 G33 Reactor Water Cleanup 1.53 l G41 Puel Pool Cooling and Cleanup 1.54 M 1.57
- M4 3 (Control Building) Fire Protection 1.58
.M50 RBSVS and Control Room A-C Chilled 2.1 Water 2.2 N 2.6 N11 Main Steam 2.7 P 2.11
.P41 Service Water 2.12
.P42 Reactor Building Closed Loop 2.13 Cooling Water 2.14
.P50 Compressed Air 2.15 1 of 2 l
t
11600.02-158e 12/22/80 058 TABLE 4.4-1 (Cont) System No. Description R 2.19
.R22 Metal Clad Switchgear 2.20
.R23 Unit Substations 2.21.
.R24 Motor Control Centers 2.22
.R35 AC Control and Instrument' Power 2.24 R36 AC Uninterruptible (Vital) Power 2.25 R41 DC Instrument Power (48 V dc) 2.26
.R42 Battery Power (125 V de) 2.27
.R43 Diesel Emergency Power 2.28 T 2.31 T23 (Ng to drywell floor Reactor Containment 2.33 seal) 2.34
.T46 Standby Ventilation System 2.35 T48 Primary Containment Atmospheric 2.36 Control System 2.37 X 2.41
.X41 '
Miscellaneous Computer, Screen- 2.42 well, Relay and Battery Room HVAC 2.43
.X60 Diesel Generator Ventilation 2.44 System 2.45
.X61 Control Room Air-Conditioning 2.46 System 2.47.
Z 2.51
.Z93 Post-Accident Monitoring 2.52 NOTES: 2.55
. Safe Shutdown Systems. 2.57
- For fire control during shutdown. 3.2 i
e 2 of 2
m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ ___ . _ . _ _ ._ _ ____ _ ___
~
- ,,,,,,,,,,, ,L ,,, ,,,,,,,,,, m u 4.4-2 sman mumenr usr I
l SAFE SHUTD06et CotPONET LIST RFVISIDH e ,* l ' iEQUIP VS CNT VS ESN) . fygg , IDENTITY DESCR1*TICH ESN CNT H0 PHR SC Plet SC LOC EQUIP LOClli AUTCHATIC DEPRESSURIZATION SYSTEM ; i 1821eSV092AX/Y AOS VLV 1821eRV-92A SOVA/S 1.41-234/7 1R42mPtLA2/82 EL 40' RELAY RH 102-218 1 1821mSV0928X/Y AOS VLV 1821eRV-928 SOVA/B 1.41-234/7 1R42ePtLA2/82 EL 40' RELAY RH 102-234 )
- IB21eSV092CX AOS VLV 1821eRV-92C SOVA 1.41-238 1R42ePtLA2 EL 40' RELAY Rtt 102-234 1821mSV0920X ACS VLV 1821eRV-92D SOVA 1.41-238 1R42ePtLA2 EL 40' RELAY Rtt 102-244
!- 1821mSV092EX/Y ADS VLV 1821eRV-92E SOVA/B 1.41-234/7 1R42ePILAZ/B2 EL 40' RELAY All 102-253 1821eSV092FX AOS VLV 1821eRV-92F SOVA 1.41-238 1R42 PILA 2 EL 40' RELAY RH 102-124 1821 5V092GX AOS VLV 1821eRV-92G SOVA 1.41-238 1R42mPtLA2 EL 40' RELAY Rtt 102-115 1821eSV092HX/Y AOS VLV 1821eRV-92H SOVA/S 1.41-234/7 1R42ePtLA2/82 EL 40' RELAY RH 102-142 1821mSvo92JX/Y ADS VLV 1821eRV-92J SOVA/B 1.41-234/7 1R42ePtLA2/02 EL 40' RELAY RH 102-124 i 1821eSV092HX/Y ADS VLV 1821eRV-92N SOVA/B 1.41-234/7 1R42ePFLA2/82 EL 40' RELAY RH 102-90
- , 1821eSV092LX/Y ADC VLV 1821eRV-92L SOVA/B 1.41-234/7 1R42mPFLA2/B2 EL 40' RELAY RH 102-270 5 3 l
l CORE SPRAY SYSTEH 1 DIVISIGH 1 EHER SHGR RH EL 25' 4-103 )l 3 1E21eP013A 1E21ePO49A CORE SPRAY PLAP HEEP FILLED PUtr 5E21A01 4E2101 1E21A01 1E21A02 1R22eSHG101 1R24ettCC117 R.S. EL 40' 8-101 l IE21mit0V031A Pulp SUCTION W 4E2102 1E21A02 1R24mitCC117 R.B. EL 40' 24-148 ! 1E21eHOV033A DISCHARGE W 4E2103 1E21A04 1R24eHCC113 R.S. EL 112' 104-115 l 1E21eHOV035A RECIRC W 4E2105 IE21A04 1R24=llCC111 R.B. EL 40' 53-108 i 1E21eHOV034A HIH FLOH W 4E2104 1E21A07 1R24mHCC117 R.B. EL 40' 14-98
- IB21ePS0234 PRES INTLN B21-H021A(H21eP004) 1.41-74 78-79 1821=PS023C PRES INTLN 821-H021CtH21mP0098 1.41-74 78-102 1E21ePDS0334 CS 0/P INTLN (H21eP001) 4E2103 1E21A04 1R24mHCC113 R.B. EL 112" 8-110 IE21 FIS002A HItt FLON (H21eP001) 6-110 f
I DIVIS10H 2 1E21eP0138 CORE SPRAY PLAP SE2102 1E21801 1R22eSHG-102 EHER SMGR RH EL 25' 4-257 1E21mP0498 HEEP FILLED PUlr 4E2101 1E21802 1R24eHCC1127 R.B. EL 40' 8-259 I 1E21stt0V0318 PLAP SUCTION W 4E2102 IE21802 1R24mitCC1127 R.B. EL 40' 24-112 i 1E21 sit 0V6338 DISCHARGE W 4E2103A 1E21804 1R24ettCC1123 R.S. EL 112' 104-245 t ! 1E21elt0V0358 RECIRC W 4F2105 1E21804 1R24ettCC1121 R.B. EL 40' 53-253 ' 1R24ellCC1127 14-242 1E21el10V0348 HIH FLOH W 4E2104 1E21807 R.B. EL 40' l t 1821ePS0238 PRES IHTLH 821-H0218tH21mP005) 1.41-77 78-257 i 1821ePS0230 PRES INTLH B21-H021DtH21mP0101 1.41-77 78-280 ! 1E21ePD50338 CS D/P INTLN (H21eP019) 4E2103 1E21A04 1R24eHCC1123 R.B. EL 112 6-248 l 1E21mFIS0028 HIH FLON (H21eP019) 6-248 1E41mP074 VActAAt PLAP 11E4101 1E41H01 1942 *tCC081 R.B. EL 40' 8-170 ]' IE41eP075 VActA24 TAtat Corm PLAP 11E4101A 1E41H02 1R42eHCC001 R.B. EL 40' 8-144 1E41mP127 AUX LO PLAP 11E4102 1E41H03 1R42mHCC081 R.B. EL 40' 4-140
- , 1E41eHOV031 HPCI PLAP SUCT FH CON ST TN W 11E4109 1E41H09 1R42eltCC081 R.B. EL 40' 20-220 1E41eHOV032 HPCI PUlr SUCT FH SUP POOL W 11E4110 1E41tl10 1R42ettCC081 R.B. EL 40' 24-210 l 1E41eHOV034 HPCI STEAH SUP OUTBRO ISO W 11E4105 1E41801 1R42mitCC082 R.B. EL 112' 44-141 j 1E41eHOV035 HPCI PutF DISCHARGE W 11E4104 1E41H04 1R42ellCC002 R.B. EL 112' 44-148 a
IE41sttOV034 HIH FLOH W 11E4112 1E41H12 1R42mitCCOB1 R.B. EL 40' 18-197 IE41stt0V037 HPCI TEST BYPASS W TO CST W 11E4107 1E41H07 1R42.ltCC001 R.S. EL 90' 18-195 1E41stt0V038 HPCI TEST BYPASS W TO CST W 11E4108 1E41H08 1R42ellCC081 R.S. EL 40' 18-205 1E41el10V039 LUB OIL COOL VV 11E4114 1E41'll3 1R42ettCC081 R.B. EL 40' 14-190 ) 4 1E41mHOV041 STEAll SUPPLY IISRD ISOL W 4E4102 1E41A01 1R42.tfCC1118 R.B. EL 112' 44-188 i 1E41et10V042 HPCI STEAll OUT BRD ISOL W 11E4103 1E41801 1R42eltCC082 R.B. EL 112' 44-192 I 1 of 13
i j TABLE 4.4-2 SWTmWN EQUIPMENT LIST l 1E41 HOV043 HPCI STEAH TO TUBINE SUPPLY W 11E4104 1E41H04 1R42eHCC081 R.B. EL 40' 17-184 1E41slOV044 HPCI TURBINE EXHAUST W 11E4114 1E41H19 1R42mitCC001 R.B. EL 40' 20-187 ..
- 1E41stOV040 HARtEJP ISOL W 11E4117 1E41H22 1R42ellCC0B2 R.B. EL 112' 44-189
- IE41eSOV081 STH LH DRH W (015-190 9 1.41-129 15-190 1E41sSOV082 STH LH DRH W (015-1901 1.41-129 15-190 1E41eSOV083 Core DISCH W 1009-184) 1.61-129 9-184 1E41aSOV095 Cote DISCH W (009-184 9 1.61-129 12-185 IE41aFS003 HPCI PP DISCH (H21mP0143 1.41-125 8-167 IB21mLIS0278 HL TRIP B21-H024BtH21aP004) 1.41-25 78-79 1821eLIS0270 HL TRIP B21-H0240tH21.P005) 1.61-24 78-297 1E41 PS021L LO PP SUCT E41-H010tH21eP0143 1.41-24 8-167 IE41=PS024A HI TURD EX E41-H017AtH21mP0141 1.41-24 8-167 1E41eP50268 HI TURS EX E41-H0178tH21mP014) 1.61 24 6-167 IE41eP50258 HI TURD EX E41-H012BtH21eP014) 1.61-24 8 167 1E41mPS0250 HI TURD EX E41-H0120tH21mP014) 1.41-24 6-167 1E41mP50238 STH PRES L E41-H001BEH21mP036) 1.41-24 6-160 1E41ePS0230 STH PRES L E41-H0010tH21eP036) 1.41-24 8-160 1E41mPD50228 HI STil D/P E41-H005 (H21m0026) 1.61-25 8-160 1E41eTE054B HI AREA T E41-H601Bl034-1853 1.41-88 34-185 1E41mTE0558 HI AREA T E41-H402B1034-2103 1.61-88 , 66-210 1E41mTE054A HI AREA T E41-NdO1A(034-100 1.41-88 34-180 1E41eTE055A HI AREA T E41-H602A6034-2003 1.41-88 34-200 IE41eP05022A HI STH D/P E41-H004 (H21*P016) 1.41-25 8-157 18218-H32A B218-H32A(H11mP6141 1.61-125 CB/d3-C12 18218-H328 B218-H328tH11mP614) 1.61-125 llG/21-H12 18318-H31A B318-H31AIB31 Pit.53A) 1.61-207 ItG/21-P12 1831B-H318 B318-H31BtB31 Pit.538) 1.41-208 6-178 1E41mPS025A HI TURB EX E41-H012A(H21aP034) 1.61-25 6-178 1E41mPS025C HI TURB EX E41-H012ClH21mP034) 1.61-25 8-157 1E41mPS023A STH PRES L E41-H001AtH21eP0143 1.41-25 8-157 IE41mPS023C STH PRES L E41-H001CIH21mP0163 1.61-25 8-157 IE41mL5092A SUPR POOL LVL 1.61-125 27-135 1E41=LS092B SUPR POOL LVL 1.61-125 27-325 1E41mLS0934 COND STRG TM-30 LVL 1.61-125 YARD 1E41=LSO938 C0 TID STRG TH-30 LVL 1.41-125 YARD 1E41 ATE 56A 44-205 1E41mTE56B d6-210 W TURB STOP A LVL SH 1.41-264 IE41eHOV043-LS4 1.41-264 17-184 IE41stt0V032-LS2 1.61-264 24-210 VV RV LL (H21-P005) 1.41-264 78-257 VV RV LL (H21-P005) 1.41-264 78-257 CNT RV HL A TRIPtH21mP004) 1.41-264 78-79 CNT llAN ISOL (H11aP4013 1.61-264 CB/63-C12 CHT TRIP SOL 1.61-200 63-208 REACTOR CORE ISOLATI0tl COOLING SYSTEH-RB DIVISION 1 1E51mP074 CONO VCOUtl Pulp 11E5101 1E51H11 1R24mitCC10A2 R.B. EL 112' 8-227 IE51mP077 C0te. C0tIDENSATE Pulp 11E5116 1E51H12 1R24mitCC10A2 R.B. EL 112' 8-230 1E51stOV031 RC PUHP SUCT FRoll CON TM W 11E5108 1E51N01 1R24aHCC10A2 R.B. EL 112' 11-217 1E51stIOV032 RCIC Pulp SUCT SUP POOL W 11E5106 1E51H02 1R24mtlCC10A2 R.B. EL 112' 24-202 1E51mit0V034 RCIC PUtP DISCHARGE W 11E5105 1E51N04 1R24mitCC10A1 R.B. EL 40' 16-200 1E51stt0V035 RCIC PUtr DISCHARGE W 11E5104 IE51H05 1R24 mitCC10 A2 R.B. EL 112' 78-193 1E51mit0V036 flIH FLOH W 11E5109 1E51H06 1R24altCC10A2 R.B. EL 112' 20-234 1E51mHOV037 TEST BYPASS W 11E5107 1E51H07 1R24mitCC10A1 R.B. EL 40' 20-201 IE51st0V038 LUDE OIL COLL. W 11E5110 1E51H06 1R24mitCC10A2 R.B. EL 112' 15-220 1E51st t0V041 RCIC STEAll SUP IteRD ISO W 6ES102 1E51A01 1R24=tlCC112B R.B. EL 112' 87-180 1E51stIOV042 RCIC STEAH SUP TO TUR O! W 11E5102 1E51801 1R24allCC10A2 R.B. EL 112' 88-180 2 of 13 f
~
- TABLE 4e4-2 SFUTDOWN EQlIIPMENT LIST .
IE51mHOV043 RCIC STEAH SUP TO TUR SUP W 11E5103 1E51H09 1R24.llCC10A2 D.B. EL 112' 11-224 1E51 HOV044 RCIC TUR TRIP AIC THROTTLE W 11E5111 1E51N10 1924allCC10A2 R.B. EL 112* 11-222 1E51.HOV045 RCIC TUR EXH TO SUP POOL W 11E5113 1E51H14 1R24eHCC10A1 R.B. EL 40' 31-217 '.**
! 1E51mit0V044 VaC PP DISCHW 11E5114 1E51N15 1R24ellCC10A1 R.B. EL 40' 29-224
! 1E51 HOV048 BYPASS W 11E5112 1E51B02 1R24altCC10A2 R.B. EL 112' 86-180 1E51 A0V081 DRAIH POT DRAIN 1.41-211 09-245 1E51eA0V083 CCic E-34 DRA!H 1.41-211 09-245 1E51eLCV095 C0to E-38 DRAIN 1.41-211 09-245 1E51eP5023A REAC PRS L E51-H019A(H21eP035) 1.41-207 40-100
. 1E51mPSO238 REAC PRS L E51-H01988H21eP038) 1.41-208 40-170 1E51eP5023C REAC PRS L E51-H019CIH21eP0351 1.41-207 40-100 IE51eP50230 REAC PRS L E51-H0190(H21mP038) 1.41-208 40-170
'IE51.PS0254 HI TURS EX E51-H012AtH21eP0173 1.41-207 8-205 1E51ePS0258 HI TURS EX E51-H012BIH21eP037) 1.41-208 8-175 1E51ePS025C HI TURS EX E51-H012CtH21eP017) 1.41-207 8-205 1E51ePS0250 HI TURS EX E51-H0120(H21eP037) 1.41-208 8-175 1E51ePD5022A HI STil D/P E51-H017 (H21eP035) 1.41-207 40-100 1E51ePDS0228 HI STil D/P E51-H018 IH21eP0383 1.41-208 40-170 1E51eTE053A HI AREA T E51 H401A 1.41-89 13-200 1E51.TE0538 HI AREA T E51-H401B 1.41-89 #
77-180 1E51.TE0544 HI AREA T E51-H402A 1.41-89 87-175 1E51eTE0548 HI AREA T E51-HdO2B 1.41-89 71-185 1821mLIS027A HI HTR LBL B21-H024A(H21eP004) 1.61-207 78-79 1821 LIS027C HI HTR LVL 821-H024C6H21eP0051 1.41-208 78-257 1E51ePS021L LO PP SUCT E51-H006 (H21eP017) 1.41-207 8-205 < IE51ePS0244 HI TURB EX E51-H009AtH21eP017) 1.41-207 8-205 1E51ePSO268 HI TUES EX E51-H009BtH21eP0173 1.41-207 8-205 1E 51ellOV043 INTLHS 1.61-207 11-224 1E51eFS003 HIH FLOH.1E51mHOV34 (H21eP017 3 1.41-208 8-205 IE 51mit0V032 INTLHS 1.41-208 24-202 1E51eTE554 HI AREA TElP E51-H025A 1.41-240 17-190 1E51eTE558 HI AREA TEIP E51-N0258 1.41-240 22-200 1E51eTE55C HI AREA TEIP E51-H025C 1.61-240 31-200 . 1E51.TE550 MI AREA TElP E51-H0250 1.41-240 31-222 j 1E51eTE56A HI AREA TElP E51-H026A 1.41-240 63-180 1E51eTE548 HI AREA TEIP E51-H0248 1.41-240 43-200
, 1E51.TE56C HI AREA TEIP E51-H026C 1.41-240 43-180 ! 1E51eTE560 HI AREA TElp E51-H026D 1.41-240 63-200 LS RCIC TRIP CHT.H1/H2tColeP-RSP) 1.61-208 63-208 LS4 RCIC TRIP CHT.TURB STP WIP-RSP) 1.41-208 63-208 IE51.LS001 H1/H2 (C61eP-R$P) 1.41-208 63-208 i CNT RCIC IHITIATE (H11eP602) 1.41-207 CB/63-C13 i
CHT RCIC TRIP 1.41-207 CHT RCIC TRIP 1.61-211 63-208 RHR SHUTD06Rt COOLING SYSTEH DIVISI0H 1 l
- IE11mP014A RHR PtRP 5E1101 1E11A01 1R22eSHG-101 EHER SHGR Rig EL 25' 8-95 1E11.P014C RHR PUIP SE1103 1E11C01 1R22eSHG-103 EHER SHGR pH EL 25' 8-80 1E11elt0V032A RHR SHUTDOHH COOL IHJECTION W dE1103 1E11A04 1R24allCC1112 R.B. EL 112' 15-083 IE11 HOV032C RHR SHUTD0624 COOL IHJECTION W dE1134 1E11C04 1R24eltCC1113 R.B. EL 112' 18-044 1E11 ell 0V033 A RHR HX SHELL SIDE Itt.ET W 4E1116 IE11A14 1R24etICC1119 R.B. EL 40' 25-105 1E11eHOV034A RHR HX SHELL SIDE BYPASS W dE1120 1E11A17 1R24ettCC1112 R.B. EL 112' 28-073 1E11mit0V035A RHR HX SHELL SIDE OUTLET W 4E1115 1E11A18 1R24eltCC1117 R.B. EL 40' 31-087 IE11ett0V03dA RHR OUTBOARD W 4E1124 1E11A19 1R24=ltCC111X R.B. EL 112' 73-092 1E11ellOV037A RHR INDOARD W 4E1125 IE11A07 1R24ellCC111X R.B. EL 112' 73-083 1E11mit0V047 RHR SilUT COOL SUCT IttB ISOS W dE1105 1E11H02 1R24altCC1118 R.B. EL 112' 84-014 01VISIDH 2 3 of 13
i I TABLE 4e4-2 SIUTDOWN EQUIPMENT LIST , ! 1E11eP0145 RHR PUF 5Ellet 1E11801 1922mSHG-102 EttER SHGR RH EL 25' 8-245 IE11eP0140 WHR PUF SE1104 1E11D01 1R22mSHG-103 EttER SHGR RH EL 25' 8-280 ., l 1E11eHOV0328 RHR SHUTD0tet COOL IHJECTICH W 4E1104 1E11804 1924e1122 R.B. EL 112
- 15-277 $
l IE11stt0V0320 RHR SHUT 00600 COOL IHJECTION W 4E1131 1E11D04 1R24e1122 R.B. EL lite 18-294 ! 1E11stt0V0338 RHR HX SHELL SIDE IttET W 4E1138 1E11814 1R24e1129 R.B. EL 40' 25-255 j 1E11ott0V0348 RHR HX SHELL SIDE BYPASS W. 4E1141 1E11817 1R24al122 R.B. EL 112' 28 288 1E11olt0V0358 RHR HX SHELL SIDE OUTLET W 4E1135 1E11818 1R24e1127 R.B. EL 40' 31-278 IE11stOV0345 RHR OUTBOARO W 4E1142 1E11819 1R24e112Y R.B. EL 112' 73-245 1 1E11eHOV0378 BHR IHBOARD W 4E1143 1E11807 1RZ4e112V R.B. EL 112' 73-243 4
! 1E11mHOV048 RHR SHUT COOL SUCT DUB ISOS W 11E1101 1E11tt05 1R42eHCC082 R.B. EL 112' 13-094 IE11=HOVOSO RHR CROSS HDR SHUT 0FF W 4E1124 1E11H01 1R24=1128 R.B. EL 112' 44-281 REACTOR RECICtA.ATION SYS FOR RHR SHUTD0604 COOLING HODE
- DIVIS10H 1 1831el10V031A RECIRC PtRP SUCT W 483102 1831A04 1R24ellCC1112 R.B. EL 112' 17-085 1831stt0V032A RECIRC PWIP OISCH W 483103 1831A07 1R24ettCC111X R.B. EL 112' 14-ES2 1
DIVISION 2 1 1831eHOV0318 RECIRC PtRF SUCT W 483107 1831804 1R24mHCC11,22 R.B. EL 112' 24-275 i 1831mHOV0328 RECIRC PulF DISCH W 453103 1831607 1R24eteCC112Y R.B. EL 112' 15-278 RHIt LON PRESSURE COOLANT IHJECTION HODE-RS DIVISION 1 IE11eP0144 RHR Pulp SE1101 1E11A01 1R22mSHG-101 EHER SMGR RH EL 25' 8-95 1E11eP014C RHR PWF SE1103 1E11C01 1922eSHG-103 EHER SHGR RH EL 25' 8-80 R.B. EL 112' 24-085 l 1E11ett0V031A RHR PUF SUCTION W 4E1101 1E11A03 1R24stsCC1113 1E11eHOV031C RHR Putr SUCTION W 4E1101 1E11C03 1R24ettCC1113 R.B. EL 112' 24-049 l 1E11el10V034A RHR HX SHELL BYPASS W 4E1120 1E11A17 1R24ettCC1112 R.B. EL 112* 28-073 i 1E11mit0V0344 RHR OUTBOARO W 4E1124 1E11A19 1R24 tlCC111X R.B. EL 112' 13-092 i 1E11mit0V037A RHR IHBOARD W 4E1125 1E11A07 1R24ettCC111X R.B. EL 112' 73-083 DIVISIGH 2 1E11eP0148 RHR Putr SE1102 1E11801 1R22mSHG-102 EHER SMGR RH EL 25' 8-245 IE11oP0140 RHR Putr SE1104 1E11001 1R22eSHG-103 EllER SHGR RH EL 25' 8-280 i 1E11sHOV0318 RHR PUtr SUCTION W 4E1129 1E11803 1R24ellCC1122 R.B. EL 112* 24-275 1E11et t0V0310 RHR Pulp SUCT1084 W 4E1102 1E11003 1R24ellCC1122 R.B. EL 112* 24-291 1E11eHOV0348 RitR HX SHELL W 4E1141 1E11817 1R24ettCC1122 R.B. EL 112' 28-288 < 4 j RHR SHUT 006et COOLING H00E , DIVIS10H 1 f 1E11sP014A RHR PuttP 5E1101 1E11A01 1R22 SHG-101 EHER SHER RH EL 25' 4-95 1 1E11eP014C RHR Putr SE1103 1E11C01 1R22eSHG-103 EHER SHGR RH EL 25' 8-80 1E11 lt0V032A RHR SHUTDO644 COOL IHJECTION W 4E1103 1E11A04 1R24etsCC1112 R.B. EL 112' 15-083 1E11 HOV032C RHR SHUTDOHN COOL INJECTION W 4E1134 1E11C04 1R24ettCC1113 R.B. EL 112' 18-044 1E11stt0V033A RHR HX SHELL SIDE IILET W 4E1114 1E11A14 1924eHCC1119 R.B. EL 40' 25-105 1E11eHOV0344 RHR HX SHELL SIDE BYPASS W 4E1120 1E11A17 1R24ettCC1112 R.B. EL 112' 28-073 1E11eHOV035A RHR HX SHELL SIDE OUTLET W 4E1115 IE11A18 1R24mitCC1117 R.B. EL 40' 31-087 i 1E11mHOV034A RHR OUTBOARO W 4E1124 1E11A19 1R24ettCC111X R.B. EL 112' 73-092 j ,IE11ett0V037A PHR INBOARD W 4E1125 1E11A07 1R24ettCC111X R.B. EL 112' 73-083 j 1E11elt0V047 RHR SHUT COOL SUCT Ite ISOS W 4E1105 1E11H02 1R24allCC1118 R.B. EL 112' 84-014 j . olv!Sr0H 2 1E11eP0148 RHR Pulp SE1102 1E11501 1R22eSHG-102 EHER SHGR RH EL 25' 8-245 1E11eP0140 RHR PUtr SE1104 1E11D01 1R22eSt!G-103 EllER SHGR RH EL 25' 8-280 1E11st:0V0328 RitR SHUTD0let COOL IHJECTION W 4E1104 1E11804 1R24mHCC1122 R.B. EL 112' 15-277 1 1E11st:0V0320 RitR SHUT 006R4 COOL IHJECTION W 4E1131 1E11004 1R24=llCC1122 R.B. EL 112* 18-294 1E11 HOV0338 RHR HX SHELL SIDE ItLET W 4E1138 1E11814 1R24ellCC1129 R.B. EL 40i 25-255
;j 4 of 13 i
TABLE 4m4-2 S}lUTDOWN EQUIPMENT LIST - 1E11mHOV0340 RHR HK SHELL SIDE BYPASS W 4E1141 1E11817 1R24attCC1122 R.B. EL 112' 28-288 1E11stOV0358 RHR HX SHELL SIDE OUTLET W 4E1135 1E11818 1R24.ttCC1127 R.B. EL 40' 31-278 .-
- 1E11etOV0368 RHR OUTBOARD W 4E1142 1E11019 1R24ettCC112Y R.B. EL 112' 73-265 ',
1E11mlOV0378 RHR INBOARD W 4E1143 1E11807 1R24allCC112Y R.B. EL 112' 73-263 1E11stt0V048 RHR SHUT COOL SUCT CUB ISOS W 11E1101 1E11H05 1R42ellCC002 R.B. EL 112' 73-096 1E11stOV050 RHR CROSS HOR SHUTOFF W 4E1124 1E11H01 1R24 ltCC1128 R.B. EL 112' 66-281 REACTOR RECICtLATIDH SYS FOR RHR SHUT 00t#( COOLING FODE DIVISIDH 1 1831mit0V031 A RECIRC PUtr SUCT W 483102 1831A04 1R24allCC1112 R.B. EL 112' 17-085 3 1831mlOV032A RECIRC PtAIP OISCH W 653103 1831A07 1R24ettCC111X R.B. EL 112' 14-082 DIVISIGH 2 1831mHOV0315 RECIRC PUIP SUCT W 483107 1831806 1R24mitCC1122 R.B. EL 112' 24-275 1831aHOV0328 RECIRC PLEP DISCH W 683103 1831801 1R24atlCC112Y R.B. EL 112' 15-278 RHR LON PRESSURE COOLANT INJECTION LODE-RB DIVISIGH 1 i. 1E11mP0144 RHR Pulp SE1101 1E11A01 1R22aSHG-101 EHER SHCR RH EL 25' 8-95 1E11mP014C RHR PUtr SE1103 1E11C01 1R22mSHG-103 EHER SHGR RH EL 25' 8-80 l 1E11mlOV031A RHR PUIP SUCTION W dE1101 1E11A03 1R24mitCC1113 R.B. EL 112' 24-085 ! 1E11stOV031C RHR PullP SUCTION W 6E1101 1E11C03 1R24mtlCC1113 R.B. EL 112' 24-069 1E11stOV034A RHR HX SHELL BYPASS W dE1120 1E11A17 1R24mtlCC1112 R.B. EL 112' 28-073 l 1E11stOV034A RHR OUTBOARD W 4E1126 1E11A19 1R24allCC111X R.B. EL 112' 73-092 ! IE11mlOV037A RHR INBOARD W 4E1125 1E11A07 1R24mHCC111X R.B. EL 112' 73-083 DIVISIGH 2 1E11aP0148 RHR PutP 5E1102 1E11501 1R22eSHG-102 EttER SMGR RH EL 25' 8-265 1E11mP0140 RHR PtAP SE1104 1E11001 1R22eSHG-103 EllER SHGR Ril EL 25' 8-280 1E11mlOV0318 RHR PUtP SUCTION W 4E1129 1E11803 1R24.ItCC1122 R.B. EL 112' 24-275 IE11ml10V0310 RHR PUtr SUCTION W 4E1102 IE11D03 1R24milCC1122 R.B. EL 112' 24-291 1E11eH040348 RHR HX SHELL W dE1141 1E11817 1R24mitCC1122 R.B. EL 112' 28-288
'.C11stOV0368 RHR OUTBOARD W dE1142 1E11819 1R24mitCC112Y R.B. EL 112' 73-245 1E11mlOV0378 RHR IHBOARD W dE1143 IE11807 1R24attCC112Y R.B. EL 112' 73-263 1E11mHOV050 RHR CROSS HOR SHUTOFF W 4E1124 1E11N01 1R24milCC112e R.B. EL 112' 66-281 RHR CONDENSING H00E-R8 1E41stOV041 STEAH SUPPLY INBOARO ISOL W 6E4102 IE41A01 1R24mitCC1118 R.B. EL 112' 46-188 1
RHR INTERLOCHS & TRIPS DIVISIDH 1 1831mP5023A LP IHTLH B31-H018A(H21mP004) 1.41-196 40-180 1821mP5023C PRES INTLH B21-H021C(H21mP0093 1.41-74 78-102 1821eP50234 PRES IHTLH B21-H021A(H21mP004) 1.41-74 78-79 1821mLIS027A LO HTR LVL B21-H024A(H21mP004) 1.41-27 78-79
.1821eL15027C LO HTR LBL B21-H024C(H21mP005) 1.41-27 78-257 1821mH83 821-H83 (H11mPd22) 1.41 219 CB/44-C12 1821mH4A B21-H6 A (H11mP609 ) 1.41-194 CB/63-C13 1821mH6C BC1-H6C (H11mP6093 1.61-194 CD/63-C13 1E11mPitS031 A PIP INTLH 1.41-220 24-85 1E11ePttS031C Pir INTLH 1.61-220 24-69 1E11mPHS032A PtP INTLH 1.61-220 14-82 1E11mPitS032C PitP INTLH 1.41-220 18-64 IE11mPOS001A ttIHFLOH IH21mP0188 1.61-219 8-15 1821mLIS029A LL/HP (H21mP004) 1.61-076 78-79 IE11aPS139A LL/HP (H21aP004) 1.61-219 78-79
! 5 of 13
TABLE 4e4-2 SIRITDOWN EQlIIPMENT LIST
,1821eLIS029C LL/HP (H21eP004) 1.41-074 78-79
' ,e DIVISIGH 2 1831eP50238 LP INTLH 831-H0188tH21mP022) 1.41-194 40-353 l PRES INTLH 821-t4021DlH21eP0010) 1.41-77 78-280 1821eP50230 1821ePS0238 PRES INTLH 821-H0218tH21eP0053 1.41-77 78-257 1821eLIS0278 LO HTR LVL 821-H02488H21eP004) 1.41-29 78-79 l 1821eLIS027D LO HTR LVL 821-H024DtH21mP005) 1.41-29 78-257 1821eH84 821-H84 (H11mP423) 1.41-194 C8/44-C12 1821eH48 821-H48 (H11eP411) 1.41-193 C8/43-C13 1821.H40 821-H40 (H11mP4113 1.41-193 C8/43-C13 1E11ePftS0318 Pip INTLH 1.41-223 24-275 1E11ePHS0310 PIP INTLH 1.41-223 24-291 1E11mPHS0328 PtP INTLH 1.41-223 15-278 i 1E11ePHS0320 PlP INTLH 1.41-223 18-294 HIHFLOH (H21eP0219 1.41-219 8-287 1E11ePD50018
, CNT HAN INTIATE 1.41-219 IE11mPS1398 LL/HP IH21eP0053 1.41-219 78-257 state 8Y LIQUID CONTROL SYSTEM ,
l i ! DIVIS10H 1 IC41eP024A SLC LIQUID CONT Pulp 4C4101 1C41A01 1R24mHCC113 R.S. EL 112* 112-148 DIVISION 2
! IC41er0248 SLC LIQUID CONT PLAIP 4C4101A 1C41801 1R24eHCC1123 R.B. EL 112' 112-144 IHTER Ch? CO2 FIRE PROT CMT. DIESEL RH 11H4304 1R42ePNL-A2. CONTROL SUILDING EL 43' 52 & C1 INTER CNT CO2 FIRE PROT CNT.8TY RH 11H4303 1R42ePl4.-A2. CONTROL SUILDING EL 43' 52 & C1 INTER CNT CO2 FIRE PROT CNT.EHER SNG RM 11H4305 1R42ePit.-A2 CONTROL SUILDING EL 43' 52 & C1 INTER CNT CO2 FIRE PROT CMT. RELAY RM 11H4304 1R42.PFL- Al EHER SHGR RH EL 25' CONTROL BUILDING EL 25' SERVICE HATER SYSTEH-PH/RB I
DIVISIGH 1 SERVICE HATER Pulp SP4101 1P41401 1R22eSHG101 EHER SHGR RH EL 25' SCREEte4 ELL EL 20' i IP41eP003A IP41eHOV031A SW DISCH W SP4101 IP41A02 1R24ellCC1110 SCRH EL 20'-4* SCREEtB4 ELL EL 20' 1P41 mil 0V032A SH HEADER 350L W 4P4103 1P41A05 1R24ellCC1110 SCRH EL 20'-4* SCREtt04 ELL EL 20' IP41eHOV033A SH CROSS TIE W 4P4108 1P41A03 1R24ellCC1119 R.S. EL 40' 30-30 1P41eHOV033C SH CROSS TIE W 6P4109 1P41C03 1R24ettCC1119 R.B. EL 40' 31-40 l 1P41el10V034A RHR HX DISCH W 6P4110 1P41A08 1R24eHCC1112 R.S. EL 112' 27-91 1P41elt0V035A 78CLCH ISOL W 4P4104 1P41A04 1R24ellCC1110 SCRH SL 20'-d' SCREEtS4 ELL EL 20' 4 1P41eHOV034A VENT CHILL ISOL W 4P4105 1P41A07 1R24allCC1114 DIESEL GEH RH EL 22' 12-44 1P41mitOV037A RBCLCH HX OUTLET W SP4107 1P41A09 1R24 llCC1112 R.B. EL 112* 23-290 l IP41eHOV039A tA.T COOLING DRH W 4P4102 IP41A04 1R24ellCC1119 R.B. EL 40' 34-044 i SH TO FUEL POOL W 4P4113 1P41A12 1R24ellCC1119 R.B. EL 40' 15-040 i IP41ellOV042A 1P41eA0V014A EttER DIESEL HX OUTLET W 4P4123 1P41A24 1R35ePNLR1 RELAY RH EL 44' CD/27-L13 l DIVISION 2 I IP41mP0038 SERVICE HATER PLAP 5F4102 1P41801 1R22eSHG102 EllER SHGR RH EL 25' SCREENHELL EL 20' 1P41mit0V0318 SHP DISCH W 4P4119 1P41802 1R24ellCC1120 SCRH EL 20*-4" SCREEl#4 ELL EL 20' IP41 IIOv0328 SH HEADER ISOL W 4P4121 1P41805 1R24ellCC1120 SCRH EL 20'-4" SCREEl#4 ELL EL 20' IP41 Il0V0338 SH CROSS TIE W 4P4108 IP41003 1R24.flCC1129 R.8. EL 40' 30-030 SH CROSS TIE W 4P4109 IP41C03 1R24.llCC1129 R.S. EL 40' 31-040 i IP41elt0V0330 IP41.Itov03 48 RHR HX DISCH W 6P4118 1P41808 1R24 llCC1128 R.B. EL 112* 27-248 IP41el10V0158 TDCLCH ISOL W 4P4120 1P41004 1R24ellCC1120 SCRH EL 20'-4" SCREEl04 ELL EL 20' IP41eHOV0348 VElaT CHILL ISOL W 6P4105 IP41807 1R24ellCC1124 DIESEL GEN RH EL 22' 12-044 IP41 mil 0V0378 ROCLCH HX OUTLET W 4P4122 IP41809 1R24ellCC1128 R.B. EL 112' 23-294 l l 6 or 13 i . 1
TABLE 4.4-2 SHUTDOWN EQUIPMENT LIST . 1P41stt0V0398 LA.T COOLItG DRH W dP4102 IP41504 1R24ettCC1129 R.B. EL 40' 34-044 IP41stt0V042B SH TO FUEL POOL W 6P4113 1P41812 1R24ettCC1129 R.B. EL 40' 15-040 ., 1P41stt0V043 FUEL POOL DRH W 6P4114 1P41H01 1R24ellCC1127 R.B. EL 40' 12-046 g i IP41eA0V0168 EttER DIESEL HX OUTLET W 4P4123 1P41D24 1R35 PtLB1 RELAY RH EL 44' CB/07-C13 DIVISION 3 1P41mP003C SERVICE HATER PtAP SP4103 IP41C01 1R22e534G103 EftER SHGR RH EL 25' SCREEte4 ELL EL 20' IP41eP0030 SERVICE HATER PtAP SP4104 1P41001 1R22eSiiG103 EHER SHGR RH EL 25' SCREEt44CLL EL 20' 1P41 tCV031C SIP DISCH W 6P4101 1P41C02 1R24=tsCC1133 EllER SHGR Ril EL 25' SCREEt#4 ELL EL 20' 1P41eHOV0310 SHP DISCH W 4P4111 1P41002 1R24 tlCC1133 EHER SHGR RH EL 25' SCREElelELL EL 20'
.1P41stOV03dC VENT CHILL ISOL W 6P4106 1P41C07 1R24ettCC1134 DIESEL GEN RH EL 22' 12-046 1P41eA0V016C EHER DIESEL HX OUTLET W 4P4124 IP41C24 1R35ePtLO1 RELAY Rif EL 25' CB/27-C13 EllERG SH TO FUEL POOL DIVISIDH 1 1G33eHOV033 RV DISCH 4G3308 1G33N12 1R24eHCC1113 EllER SHGR RH EL 25' 121-190 DIVISION 2 1G33 mil 0V034 RV DISCH W 11G3301 1633H13 1R24eHCC0p2 R.B. EL 112' 121-190 REACTOR HATER CLEAN-UP SYSTElf DIVISION 1 1G41stIOV032A SERVICE HTR IfLET W 4G4103 1G41A04 1R24eHCC1114 EHER SHGR RH EL 25' 162-147 DIVISI0H 2 1G41el10V0328 SERVICE HTR ItLET W 4G4103 1641504 1R24eHCC1124 R.B. EL 150' 162-149 RBCLCH SYSTEH-RB DIVISION 1 IP42eP005A RBCLCH COOLING HATER PUtP 4P4201 IP42A01 1R24ettCC1112 R.B. EL 112* 150-t#4 IP42etOV042A RBCLCH HX ItLET W 6P4214 1P42A10 1R24ettCC1112 R.B. EL 112' 30-349 DIVISIDH 2 1P42.P0055 RBCLCH COOLItG HATER PtAP 6P4202 1P42501 1R24ettCC1122 R.B. EL 112' 30-352 IP42 tt0V0428 RECLCH HX ItLET W 6P4218 IP42B10 1R24ellCC1128 R.B. EL 112' 150-tei DIVISIGH 3 1P42eP005C RBCLCH COOLItG HATLR PUFF 6P4203 IP42C01 1R24ettCC1131 R.B. EL 43' 150-NE EllERGENCY GENERATOR-EGR DIVISION 1 1R43 G-101 EDG G101 PROT-GEH DIFF CNT 8R4301 1R43A03 DG Rit/22-L15 1R43.G-101 VR CT G-101 PROT ed4301 1R43A24 DG RtV22-L15 1R43.G-101 EHER DG 51/40/32 PROT 8R4301 1R43A05 DG RIV22-L15 1R43.G-101 EHER DG SON Grio PROT 8R4301 1R43A28 DG Rtt/22-L15 1 1R43.G-101 CURRENT TEST BCH AtO RESIS BOX ER4301 1R43A27 DG Ril/22-L15 1R43.G-101 GOVEtCR HYDRAULIC ACTUATOR 11R4302 1R43A23 1R42mPit-Al EttER SHGR RH EL 25' DG Ril/22-L15 1R43 G-101 EG-A COtIT BOX AtO 190T OP POT *8R4301 1R43A06 EttER SilGR Rlt EL 25' DG Rit/22-L15 1R43mG-101 VR CT G-101 PROT 8R4301 1R43A25 EltER SHGR RH EL 25 DG Rit/02-L15 1R43eG-101 VOLT REGULATCR 894305 1R43A26 EllER SHGR Rtt EL 25' DG Ril/02-L15 1R43 G-101 START CIRCUIT 11R4301 1R43A12 1R42mPtt-Al EttER SHGR Rig EL 25' DG Ril/22L-15 1R43.G-101 START CIRCUIT 11R4301 1R43A22 1R42ePit-Al EttER SI:GR Rit EL 25' DG Rit/22-L15 1R43.G-101 START CIRCUIT 11R4302 1R43A23 1R4:ePit-Al EllER S;3GR Rtl EL 25' DG Rit/22-L15 DIVI 510tl 2 1R43eG-102 EDG G102 PROT-GEN DIFF CHT 8R4302 1R43803 EttER SHGR Rif EL 25' DG Rit/22-C15 7 of 13
, TABLE 4e4-2 SIUTDOWN EQUIPMENT LIST 1943 G-102 EHER DG 51/40/32 PROT 8R4302 1943805 EHER SHGR RH EL 25' DG RIV22-C15 '
1R43eG-102 EHER DG SON Gie PROT 8R4302 1R43828 EHER SHGR RH EL 25' DG Rit/22-C15 , 1943eG-102 CtNIRENT TEST BCM Are RESIS BOX 8R4302 1R43827 EllER SHGR RH EL 25' DG Ril/22-C15 *e
'1R43eG-102 GOVEHOR HYDRAULIC ACTUATOR 11R4304 1R43823 1R42ePPL-81 EllER SHGR Ril EL 25' DG Rtt/22-C15
~ 1R43eG-102 EG-A CONT 80X AHD HOT OP POT 8R4302 1R43804 EttER SHGR RH EL 25' DG RIV22-C15 i 1943eG-102 VR CT G-102 PROT 8R4302 1R43825 EllER SHGR RH EL 25' DG RIV22-C15 1R43eG-102 VOLT REGULATOR 8R4306 1R43B24 EllER SHGR Ril EL 25' DG Ril/22-C15
,1R43 G-102 VR CT G-102 PROT 8R4302 1R43824 EllER SHGR RH EL 25' DG RIV22-C15
,1R43 G-102 START CIRCUIT 11R4303 1R43812 1R42ePtL-81 EllER SHGR Ril EL 25' DG RIV22-C15 i i1R43eG-102 START CIRCUIT 11R4303 1R43822 1R42ePit-81 EttER SHGR RH EL 25' DG Ril/22-015 i !1943eG-102 STARY CIRCUIT 11R4304 1R43823 1R42ePit-81 EllER SHGR Rig EL 25' DG RH/22-C15 DIVISION 3 l '1R43 G-103 EDG G103 PROT-GEN DIFF CMT 8R4303 1R43C03 DG Ril/22-L15
- i1R43eG-103 EHER DG 51/40/32 PROT 8R4303 1R43C05 DG RH/22-L15 l 1R43eG-103 EllER DG 50N GND PROT 8R4303 1R43C28 DG Rtt/22-L15 I i1R43 G-103 CURRENT TEST BCH AHD RESIS 80K 8R4303 1R43C27 GG RIV22-L15 I 1R43eG-103 GOVEHOR HYDRAULIC ACTUATOR 11R4304 1R43C23 1R42ePtt-C1 EHER SHGR RH EL 25' OG plV22-L15 j 1R43.G-103 EG-A CONT S0X AND HOT OP POT 8R4303 1943C06 EllER SHGR RH EL 25' DG RIV22-L15 t 1943eG-103 VR CT G-103 PROT 8R4303 1R43C25 i EHER SHGR RH EL 25' DG RIV22-L15 1R43eG-103 VOLT REGlA.ATOR 8R4307 1R43C24 EttER SHGR RH EL 25' DG RIV22-L15 1R43.G-103 VR CT G-103 PROT 8R4303 1R43C24 EllER SHGR RH EL 25' DG Rit/22-L15
. 1R43eG-103 START CIRCUIT 11R4305 1R43C12 1R42mPtL-C1 EllER SHGR Ril EL 25' DG Ril/22-L15 1R43.G-103 START CIRCUIT 11R4305 1R43C22 1R42ePIL-C1 EttER SHGR RH EL 25' DG Rit/22-L15 1R43 G-103 START CIRCUIT 11R4306 1R43C24 1R42ePIL-C1 EHER SHGR RH EL 25' DG plV22-L15 i DIESEL FUEL TRANSFER SYS-EG8 DIVISION 1 1R43eP-2014 EG FUEL OIL TRANSFER PtRP 4R4304 1R43A09 1R24elCC1114 DIESEL CEN RH EL 22' YARD 1R43eP-202A EG FUEL OIL TRANSFER PUIP 4R4304 1R43A10 1R24ellCC1116 DIESEL GEN RH EL 22' YARD DIVISION 2 j 1R43eP-2018 EG FUEL OIL TRANSFER PtRP 4R4305 1943809 1R24mitCC1126 DIESEL GEN RH EL 22' YARD ! 1R43eP-2028 EG FUEL OIL TRANSFER PUIP 4R4305 1R43810 1R24ettCC1126 DIESEL GEN Ril EL 22' YARD l DIVISION 3 j 1R43eP-201C EG FUEL OIL TRANSFER PtRP 4R4306 1R43C09 1R24ellCC1134 DIESEL GEN RH EL 22' YARD 1R43eP-202C EG FUEL DIL TRANSFER PUIP 6R4304 1R43C10- 1R24allCC1134 DIESEL GEN Ril EL 22' YARD HVAC SYSTEHS i CRAC/R85VS CHILL HATER SYSTEH-C8 i DIVISION 1 2 lil50eP1374 CHILLED HATER PLRP 4415001 1H50A08 1R24eHCC1114 DIESEL GEN RH EL 22' C8/43-L12 lil50eP139A COND HATER PtRIP 4185003 Ill50A10 1R24eHCC1116 DIESEL GEN RH EL 22' CS/63-L12 4 Ilt50eP231A LUBE OIL PUIP 6815011 Ill50A14 1R24ellCC1116 DIESEL GEN Ril EL 22* CB/63-C16
- IHSonHC0034 HATER CHILLER Sil5001 IltSOA01 1R22eSHG101 EllER SHGR RH EL 25' CB/63-L12 lil50eHC0034 CHILLER COHTROLS Sil5001A Ill50A03 1R35ePit-R1 RELAY Ril EL 44' C8/63-L12 Itt50ett0V0314 RETURH W 4ttS005 Ilt50A04 1R24ellCC1116 DIESEL GEN RH EL 22' C8/71-L13 IH50ett0V0324 StPPLY W 4tl5004 IltSOA05 1R24ellCC1116 DIESEL GEN RH EL 22' CB/75-L13 Ill50eHOV033A RET X0VER W 4tl5007 1H50A04 1R24ettCC1116 DIESEL GEN RH EL 22' C8/75-L13 Ill50 ell 0V034A SUP X-0VER W 4415008 11150 A07 1R24allCC1114 DIESEL GEN RH EL 22' C8/75-L13 Ill50eA0V068A ISOL BYPASS W 6415009 Ill50A12 1R35ePit-R1 RELAY Ril EL 44' CB/71-L12 Ilt50eA0V0694 ISOL SYPASS W 6tl5010 Ill50A13 1R35ePIL-R1 RELAY Ril EL 44' C8/75-L12 f
I DIVISION 2 1H50eP1378 CHILLED HAIER PLRP 6115001 1H50808 1R24ettCC1126 ' DIESEL GEN Ril EL 22' C8/63-L13 q lil50eP1398 C0tB HATER PUIP 6l15003 11150810 1R24eHCC1124 DIESEL GEN Ril EL 22' C8/43-L13 8 of 13
~
TABLE 4.4-2 SHUTDOWN EQUIPMENT LIST . 1H50 P2318 LUBE OIL PU P 6ttS011 11150814 1R24st1CC1124 DIESEL GEH Ril EL 22' CB/63-L13 lits 0eHC0038 HATER CHILLER 5115002 Ilt50B01 1R22.SHG102 EttER SHGR Ril EL 25' CB/63-L13 . ,, lits 0eHC0038 CHILLER CCHTROLS Sits 002A 1H50B03 1R35ePit-B1 EttER SHGR Rtl EL 25' CB/63-L13 . 1H50eHOV0318 RETURN W 4185005 18t50B04 1R24ellCC1126 DIESEL GEN Rf1 EL 22' CB/ 71-L13 2 1H50ml10V0328 SUPPLY W 4115006 1150B05 1R24 ettCC1126 OIESEL GEN Ril EL 22' CB/75-L13 IttSoettav033B RET X-0VER W 6115007 1t150306 1R24 HCC1126 DIESEL GEN RH EL 22' CB/75 L13 1H50 ell 0V0348 $UP X-0VER W 6115008 lits 0807 1R24 IICC1126 O!ESEL GEH Ril EL 22' CB/71-L13 lits 0e A0V0468 ISOL BYPASS W 6ftS009 lits 0812 1R35 Pft-B1 RELAY RH EL 44' CB/71-L13 IttS0 e A0V0698 ISOL BYPASS W 6115010 1H50B13 1R35ePtL-B1 RELAY RH EL 44' CB/75-L13 e = OIVISION 3 19tS0eP140A Corc HATER PGP 6H5004 Itt50A11 1R24ettCC1134 DIESEL GEN Ris EL 22' CB/63-L12 lil50 P1408 C0tO HATER PUIP 6H5012 Ilt50C14 1R24 ttCC1134 01ESEL GEH RH EL 22' CB/63-L13 1H50eP233A LUBE OIL PUIP 6tt5012 Ilt50C14 1R24=llCC1134 DIESEL GEH Ril EL 22' CB/63-L15 lits 0eP233B LUBE OIL PO P 6t15012 18150014 1R24eHCC1134 DIESEL GEH Ril EL 22' CB/63-L12 IH50eHC004A HATER CHILLER 5115003 Itt50C01 1R22eSHG103 EllER SHGR RH EL 25' CB-63-L12 1H50eHC0048 HATER CHILLER 5:15004 18t50001 1R22eSHG103 EllER SHGR RH EL 25' CB/63-L13 lits 0 HC004A CHILLER CONTROLS Sits 003A IltSOC03 1R 35.PtL-01 RELAY Ril EL 44' CB/63-L12 IltS0eHC0048 CHILLER CONTROLS Sits 004A 18150003 1R35ePtL-01 RELAY RH EL 44' CB/63-L13 e RBSVS SYSTEll-RS DIVIS10H 1 IT4deUC002A ui!T COOLER 4T4619 1T46A13 1R2'4ellCC1118 R.5. EL 112' 8-332 IT46.UC003A UNIT COOLER 6T4620 1T46A14 1R24ellCC1118 R.B. EL 112' 8-81 IT46 UC004A REFUEL LVL UC 4T4621 IT46A15 1R24allCC1112 R.B. EL 112' 218-60 1T46eUC005A REFUEL L41 UC 4T4622 1746A16 1R24 flCC1112 R.B. EL 112' 218-323 IT46.UC020A RB ttCC RH UC 4T4625 IT46A23 1R24 IICC1118 R.B. EL 112' 112-80 1T46eUC021A tG Ril 111 112 UC 4T4626 IT46A33 1R24etICC1114 R.B. EL 150' 150-22 CMT RBSVS/CRAC ACC SIGNAL 11T4601 IT46A19 CB/48-C14 CNT RBSVS IHITIAT SIGitAL 11T4602 CB/48-C14 DIVISION 2 IT46eUC0028 UNIT COOLER 4T4619 1T46B13 1R24=tlCC1128 R.8. EL 112' 40-275 1T46eUC0038 UNIT COOLER 6T4620 1144B14 1R24eHCC1128 R.8. EL 112' 40-85 IT46eUC0048 REFUEL LVL UC 4T4621 IT44815 1R24ellCC1122 R.8. EL 112' 218-143 IT46 UC0058 REFUEL LVL UC 6T4622 1T46B16 1R24altCC1122 R.B. EL 112' 218-240 1T44.UCO208 RH IICC RH UC 6T4625 IT46B23 1R24et1CC1126 R.B. EL 112' 112-227 IT46 UCO218 HG RH 111 112 UC 6T4626 1746B33 1R24eHCC1127 R.B. EL 40' 150-340 CHT RBSVS/CRAC ACC SIGNAL 11T4601 IT46B19 CB/48-C14 CHT RBSVS INITIAT SIGNAL 11T4403 CB/48-C14 DIVISIDH 3 IT46.UC022B IG RH 113 UC 4T4627 IT46B34 1R24ellCC1131 R.8. EL 63' 161-340 1T46eUC022A IG RH 113 UC 6T4627 IT46A34 1R24ellCC1131 R.S. EL 63* 161-22 CNT RBSVS INITIAT SIGNAL 11T4604 ESHG R00ft/25-H13 RELAY /SHGR ROOH VENT SYSTEH-CB OIVISIGH 1 IX41eACUO14A CHILL HT COOL 6X4125 IX41A01 1R24eHCC1114 OIESEL GEN RH EL 22' HVAC/44-C14 1X41=H000354 CHILL HT COOL 6X4125 1X41A01 1R24allCC1116 DIESEL GEH Ril EL 22' HVAC/53-C12 1X41eFN029A RELAY Ril EXHAUST FAH 4X4121 IX41A02 1R24etICC1116 01ESEL GEN Ril EL 22' HVAC/44-C13 DIVISIDH 2 IX41eACU0148 CHILL HT COOL 4X4125 IX41801 1R24ettCC1126 DIESEL GEN RH EL 22' HVAC/44-C13 1X41eHOD0358 CHILL HT COOL 6X4125 1X41B01 1R24 11CC1126 DIESEL GEH Ril EL 22' HVAC/55-C12 IX41 FH0298 RELAY Ril EXHAUST FAN 6X4121 IX41002 1R24altCC1126 DIESEL GEN Rif EL 22' HVAC/44-C13 CHILLER EQUIP RH VEtiT SYSTEH-C8 9 of 13
.. e TABLE 4.4-2 SHUTDOWN EQUIPMENT LIST 4
DIVISIDH 1 . . 1X41eFH039A RBSV CHILL EQUIP RH FAH 4X4124 IX41A19 1R24ellCC1114 DIESEL GEN RH EL 22' HVAC/43-C39 e 1X41eH00031A RBSV IHTAHE DA6FER 4X4126 IX41A19 1R24etICC1116 DIESEL GEN RH EL 22' HVAC/43-L16 IX41ml100032A RBSV EXHAUST DAIFER 6X4126 1X41A19 1R24ettCC1116 DIESEL GEH RH EL 22' HVAC/63-L16 DIVISIGH 2 1X41mFH0398 RBSV CHILL EQUIP RH FAN eX4127 IX41819 1R24ettCC1126 DIESEL GEN Ril EL 22' HVAC/63-C15 1X41eH000318 RBSV IHTAHE DAIFER 6X4127 1X41819 1R24ellCC1126 DIESEL GEN Rtl EL 22' HVAC/63-L14 1X41=tt000328 RBSV EXHAUST DAIFER 4X4127 1X41819 1R24sttCC1126 DIESEL GEH Ril EL 22' HVAC/43-L16 BATTERY ROOH VENT SYSTEH-CB
. DIVISIDH 1 l 1X41eFH072A BTY Rtl VENT FAH 4X4128 1X41A03 1R24milCC1115 EHER SHGR RH EL 25' CB/30-H16
- 1X41mit00039A BTY RH DISCHARGE DAtFER 6X4128 1X41A03 1R24milCC1115 EllER SHGR RH EL 25' CB/27-H14 1X41stt00040A BTY RH EXHAUST DAIFER 4X4128 1X41A03 1R24allCC1115 EllER SHGR RH EL 25' CB/30-H16 1X41 ell 00041A STY Ril EXHAUST DAIFER 4X4128 1X41A03 1R24ellCC1115 EllER SHGR RH EL 25' CB/26-H16 DIVISION 2 ,
1X41eFH0725 BTY RH VENT FAN 4X4129 1X41803 1R24ettCC1125 EHER SHGR RH EL 25' CD/30-C16 IX41eHOD0398 BTY RH DISCHARGE DA6FER 6X4129 1X41803 1R24ellCC1125 EllER SHGR RH EL 25' CB/29-C16 1X41mH000408 BTY RH EXHAUST DAIFER 4X4129 1X41803 1R24ellCC1125 EllER SHGR RH EL 25' CB/30-C16 IX41eH000418 BTY Rtl EXHAUST DAIFER 4X4129 1X41803 1R24mitCC1125 EltER SMGR RH EL 25' CB/26-C16 DIVI 510H 3 IX41eFil072C BTY Rtl VENT FAN 4X4130 1X41CO3 1R24ettCC1133 EttER SHGR RH EL 25' CB/39-H16 IX41stt00039C BTY Ril DISCHARGE DAIFER 6x4130 1X41C03 1R24ettCC1133 EttER SHGR RH EL 25' CB/37-H14 1X41mH00040C STY RH EXHAUST DAIFER 4X4130 1X41C03 1R24ettCC1133 EllER SHGR Ril EL 25' CB/41-C16 1X41mit00041C BTY RH EXHAUST DAIFER 4X4130 1X41C03 1R24mitCC1133 EllER SHGR RH EL 25' CB/35-H16 EHERGENCY GEN ROOH VENT SYSTEH-EGB DIVISIDH 1 IX41 FH025A FILTER BOAST FAN 4X4102 1X61A02 1R24allCC1116 DIESEL GEH RH EL 22' EGB/43-C12 IX60mFH028A EtIER VENT FAN 4X4002 IX60A02 1R24ettCC1116 DIESEL GEH RH EL 22' EGB/22-L15 IX60eH0031A DAIFER 4X4002 1X40A02 1R24ellCC1116 DIESEL GEN RH EL 22' EGB/38-L16 1X60ett0032A DAIFER 4X4002 IX60A02 1R24eHCC1114 DIESEL GEN Ril EL 22' EGB/34-L12 DIVISIDH 2 1X81eFH0258 FILTER BOAST FAH 4X4102 IX41502 1R24eHCC1126 DIESEL GEH RH EL 22' EGB/63-C12 IX60eFH0285 EllER VENT FAN 4X4003 IX60B02 1R24ellCC1124 DIESEL GEN Ril EL 22' EGB/22-L15 IX40et:0031B DAIFER 4X6003 1X60B02 1R24stICC1126 DIESEL GEN Ril EL 22* EDG/38-L16 l 1X40eH00325 DAIFER 6X4003 1X40002 1R24ellCC1126 DIESEL GEN Rtl EL 22' EDG/CA12 DIVISIDH 3 IX40eFN028C EHER VENT FAN 6X6004 IX40C02 1R24ellCC1134 DIESEL GEN RH EL 22' EDG/22-L15 , 1X60mit0031C DAIFER 6X4004 IX60CO2 1R24ettCC1134 DIESEL GEN Ril EL 22' EDG/38-CA14 l 1X60stt0032C DAIFER 6X6004 IX60C02 1R24=lt:C1134 DIESEL GEH Ril EL 22' EDG/34-CA12 l SCREEN HELL PUlr HOUSE VENT l j DIVISION 1 IX41 FH048A PP llS FAN 6K4118 1X41A15 1R24ettCC1110 SCREEte4 ELL EL 20' DIVISI0H 2 1X41eFH0685 PP HS FAH 4X4119 1X41815 1R24ellCC1120 SCREEtelELL EL 20' CONTROL RO0tt AIR COllDITIONING SYSTEll-CB i 10 of 13
I TABLE 4e4-2 SHUTDOWN EQUIPMENT LTST . DIVISIDH 1 IX41oHOV031A CRAC ISOL W 4X4104 IX41A05 1R24=llCC1115 EllER SHGR PH EL 25' CB/78-C12 g IX41eHOV32A CRAC ISOL W 4X4110 1X61A09 1R24ellCC1115 EllER SHGR RH EL 25' CB/47-C16 -e IX61eA0v36A CRAC NORH AIR IffTAME W 4X6104 1X61A04 1R35ePIL-R1 RELAY R00ll EL 44' C8/66-C16 IX41mA0V304 CRAC ISOS W 4X4108 IX61A03 1R 35ePIL-R1 RELAY ROOld EL 44' C8/73-C16 1X61eACU70A CRAC IktIT 4X6101 1X61A01 1R24ellCC1114 DIESEL GEH Ril EL 22' CB/71-C13 1X61dOO34A CRAC UNIT DAIFER 4X6101 1Xd1A01 1R24allCC1114 DIESEL GEN RH EL 22' CE/77-C16 IX61eTCV021A CRAC-COOLING COIL W 13X6101 1X61A10 C8/71-C13 CNT CRAC EllER INIT SIGH IPtt VX11 11X4101 1X41A07 1R42ePtL-AZ CB/44-C12 IX41 ETIC 021A CRAC ACUO7A COOLING CONTROL 13X4101 1X61A10 CB/43-H12 IX61eTE021A CRAC TElF ELEllENT 13X4101 1X41A10 CB/67-12H 1X41mA0V0394 ISOL DAIFERS 4X6109 1X61A04 1935ePit-R1 RELAY RH EL 44' CB/77-C14 IX61eFH0254 FILTER BOASTER FAN 4X6102 1X61A02 1R24allCC1114 DIESEL GEH RH EL 22' C8/63-C12 IX61mlOOO33A FILTER BOASTER FAN DAIPER 4X4102 IX61A02 1R24ettCC1116 DIESEL GEH RH EL 22' CB/77-C12 OIVISION 2 IX41eHOV0318 CRAC ISOL W 4X4105 1X41805 1R24eHCC1125 EllER SHGR RH EL 25' C8/78-C12 IX41stOC0328 CRAC ISOL W 4X6111 IX41809 1R24ellCC1125 EHER SHGR RH EL 25' CB/70-C16 IX41mA0V368 CRAC HORil AIR IHTAME W 4X6104 1X41804 1R35ePit-B1 RELAY Rig EL 44' CB/70-C16
-1X61eA0V386 CRAC ISOL W 4X6108 1X61803 1R35ePit-01 RELAY RH EL 44' C8/73-C14 1X41mAUC708 CRAC UNIT 4X6101 IX61801 1R24=ltCC1124 DIESEL GEN RH EL 22' CB/71-C13 IX41= LOO 345 CRAC UNIT DAIFER 4X4101 1X41801 1R24eHCC1126 DIESEL GEH Ril EL 22' CB/77-C16 1X61eTCV0218 CRAC-COOLING COIL W 13X6102 IX61810 CB/71-C13 CNT CRAC EHERG INIT $1GH (Ptt VX11 11X6102 1X41807 1R42ePit-BZ C8/44-C12 IX41 ETIC 0218 CRAC ACU708 COOLING CONTROL 13X4102 IX41810 CB/43-H12 1X61mTE0218 CRAC TEHP ELEHENT 13X6101 IX61810 CB/67-H12 1X41eAPV0398 ISOL DAIFERS 4X6109 1X41604 1R35ePtL-81 RELAY RH EL 44' IX61eFN0258 FILTER 80 ASTER FAN 4X6102 1X41802 1R24ellCC1126 DIESEL GEN RH EL 22' CB/43-C12 1X61slOOO338 FILTER BOASTER FAH DAIFER 6X6102 1X61802 1R24ellCC1124 DIESEL GEN RH EL 22' CB/74-C12 COlFRESSED AIR SYSTEH DIVISIDH 1
- 1P50eHOV104 INSIR AIR TO SUPPR CHAleER W 6P5012 1P50H05 1R24eHCC1112 R.B. EL 78' 30-250 IP50eHOV103A COlFRESS AIR SRV OUTBRD ISOL W 6P5014 IP50A12 1R24ettCC1112 R.B. EL 112' 90-250 IP50mlOV105A COlFRESS AIR SRV IteRD ISOL W 6P5014 1P50A13 1R24ellCC1113 R.B. EL 112' 75-220 1P50etOV113A COlFRESS AIR SRV NORilAL SUP W 6P5018 1P50A14 1R24ellCC1112 R.S. EL 112' 90-250 1P50etOV1144 COlFRESS AIR SRV EllERG SUP W 6P5020 1P50A15 1R24ellCC1118 R.B. EL 1128 90-250 1P50ePS113A SERVICE AIR HEADER f40RilAL SUP 1.41-273 151-170 1P50ePS1054 SERVICE AIR HEADER PRESSURE 1.41-272 151-155 i
DIVISION 2 1P50eHOV106 INSTR AIR TO SUPPR CHAllBER W 4P5013 1P50H07 1R24=HCC1129 R.B. EL 40' 30-250 1P50mlOV1035 ColFRESS AIR SRV OUTBRO ISOL W 6P5015 1P50812 1R24=llCC1122 R.B. EL 40' 90-070 l IP50eHOV1058 COlFRESS AIR SRV IHBRO ISOL W '4P5017 1P50B13 1R24ettCC1122 R.B. EL 112' 89-255 t IP50ett0V1138 ColFRESS AIR SRV NORilAL SUP W 6P5019 IP50814 1R24eHCC1123 R.B. EL 112' 151-220 1P50ml10V1148 ColFRESS AIR SRV EHERG SUP W 4P5015 1P50815 1R24ettCC1123 R.B. EL 112' 89-070 1P50ePS113B SERVICE AIR HEADER tORitAL SUP 1.41-273 151-220 IP50ePS1058 SERVICE AIR HEADER PRESSURE 1.61-272 151-220 . j SHGR HCC PtLS-CR/RB/PH DIVISIDH 1 1R22eSHG101 4160V-HVH RHR SH CS SHG111 FE-1B LL 25' ACB 101-1 EllERG BUS NORH SUPPLY SR2209 1R22A01 1R22 SHG101 EHER SHGR RH EL 25' EL-25' s.C8 101-2 EllER BUS RES SUPPLY SR2210 1R22A02 1R22eSHG101 EHER SHGR RH EL 25' EL-25' BUS 101 SEQ PROGRAll CHT SH RllR CS HVH SR2217 1R22A03 Ell [R SHGR RH EL 25' EL-25' BUS 4160 REL & HET CHT 8R1205 1R22A04 1R22eSHG101 EllER SHGR RH EL 25' EL-25' DIVISIDH 2 11 of 13
TABLE 4.4-2 SHUTDOWN EQUIPMENT LTST II22eSHG102 4160V-HVH RHR SM CS SHG112 EllER SHGR RH EL 25' EL-25' ! ACB 102-1 EtERG BUS HORH StFPLY SR2211 1R22801 1R22eSHG102 EllER SHGR RH EL 25' EL-25' ; 'I ACB 102-2 EHERG BUS RES SUPPLY 5R2212 1R22802 1R22mSHG102 EttER SHGR RH EL 25' EL-25' . SR2218 1R22B03 EHER SHGR RH EL 25' EL-25' l BUS 102 SEQ PROGRAH CNT SH RHR CS , BUS 4160 REL & itET CHT 8R2206 1R22804 1R22eSHG102 EHER SHGR RH EL 25' EL-25' ! DIVISICH 3 . , 1122eSHG103 4160V-HVH RHR SH SHG113 FE-1AV 1R'42 ePNL-C1 EttER SIGR RH EL 25* EL-25' ACB 103-1 EHERG BUS NORH SUPPLY 5R2213 1R22C01 1R22 SHG103 EllER SHGR Ril EL 25' EL-25' ACB 103-2 EttERG BUS RES SUPPLY 5R2214 1R22C02 1R22eSHG103 EltER SHGR Ril EL 25' EL-25' BUS 103 SEQ PROGRAH CNT SH HVH SR2219 1R22CO3 EllER SHGR RH EL 25' EL-25' BUS 4160 REL 7 IIET CMT 8R2207 1R22C04 1R22eSHG103 EllER SHGR RH EL 25' EL-25' DIVISION 1 f.CB 101-4 FEEDER TO EHERG BUSS 111 5R2303 1923A01 1R22eSHG101 EllER SHGR Ril EL 25' EL-25' 1%23mT-101 TRANSFORitER FE-1B 1R22.SHG101 EllER SHGR RH EL 25' EL-25' 1*23 SHG111 480V -1R24allCC1110-91PtLR1 EllER SIGR RH EL 25' EL-25' 1JBe701 1R24ellCC1111/9 FE-1E 1R23eSHG-111 EttER SIGR Rtl EL 25' EL-25' IJBe703 1R24ettCC1117/4/Y/Z/A/C FE-1E 1R23eSHG-111 EllER SHGR RH EL 25' EL-25' IJBe300 IJ8e701/3 FE-1E 1R23mSHG-311 EllER SHGR RH EL 25' EL-25' 1JBe702 1R24eHCC1113/8 FE-1E 1R23eSHG-111 EttER SHGR Ril EL 25' EL-25' DIVISIDH 2 ACB 102-4 FEEDER TO EftERG BUS 112 SR2304 1R23801 1R22eSHG102 EHER SHGR RH EL 25' EL-25' 1R23eT-102 TRANSFORitER FE-18 1R22eSHG102 EllER SHGR RH EL 25' EL-25' 1R23mSHG112 480V -1R24mHCC1120-9EPitB1 EttER SHGR RH EL 25' EL-25'
, IJBe706 1R24ellCC1127/4/X/A/C FE-1E 1R23mSHG-112 EllER SHGR Ril EL 25' EL-25' 1JBe704 1R24ettCC1121/9 FE-1E 1R23eSHG-112 EltER SHGR Ril EL 25' EL-25' IJBe301 IJBe704/6 FE-1E 1R23eSHG-112 EllER SIGR Ril EL 25' EL-25' IJBe705 1R24mitCC1123/8 FE-1E 1R23.SHG-112 EttER SHGR Rif EL 25' EL-25' DIVISIGH 3 ACB 103-5 FEEDER TO EllERG BUS 113 SR2305 1R23C01 1R22mSHG103 EHER SHGR Rig EL 25' EL-25' 1R23eSHG113 480V -1R24allCC1131-41PtLO1 EllER SHGR Ril EL 25' EL-25' 1R23nT-103 TRANSFCRitER FE-1B 1R22mSHG103 EllER SHGR RH EL 25' EL-25' DIVISICH 1 1R35ePtLR1 120V -HVH SH 1R35A02 1R29mitCC1115 EllER SHGR Ri1 EL 25' EL-25' 1924mitCC1110 480V -X41.P41 EllER SHGR Ri1 EL 25' EL-25' 1R24 llCC1111 480V -E11.E21 EttER SHGR Ril EL 25' EL-25' i 1R24mitCC1112 480V -831.P42.T46.E11 FE-1E 1R23eSHG-111 EltER SHGR RH EL 25* EL-25' 1R24mitCC1113 480V -E21.G33.C41.E11 EllER SHGR RH EL 25' EL-25' 1R24sttCC1114 480V -G41 FE-1H 1R24mSHG111 EttER SHGR Ril EL 25' EL-25' 1RZ4=ttCC1115 480V -R42.R35.X41.X61. FE-1E 1R23mSHG-111 EllER SHGR Ril EL 25' EL-25' 1R24mitCC1116 480V -It50.P41.R43.X41.X60.X61 FE-1E 1R23eSHG-111 EliER SHGR RH EL 25' EL-25' 1R24mitCC1117 480V -E11.E21 EllER SHGR Ril EL 25' EL-25' 1R24eltCC1118 480V -E41.E11.T46 FE-1H/H 1R23mSHG111 EttER SHGR Rtl EL 25' EL-25' 1R24altCC1119 480V -E11.P41 FE-1H 1R23mSIG111 EltER SHGR Ril EL 25' R.B. EL 40' 1R24ettCC111X 480V -E11.B31 FE-1H 1R24eTRS111X R.B. EL 112' R.B. EL 112'-6' 1R24sttCC111Z FE-1H 1R24ettCC111Y R.B. EL 78' R.B. EL 112'-6' 1R24=TRS111Y TRAttSFER SHITCH FE-1E R.B. EL 112'-6' 1R24eTRS111X TRANSFER SHITCH FE-1E 1R24ettG113A/111 R.B. EL 150' 1RZ4stG-111 110 TOR GENERATOR FE-1E 1R23nS4G-111 EllER SHGR RH EL 25' R.B. EL 150' IJBe703 1R24ellCC111Y/7/4/Z FE-1H 1R24eSHG111 EllER SHGR RH EL 25' EL 8' DIVISION 2 1R24ettCC1120 480V -P41.X41 EllER SHGR RH EL 25' SCREEte4 ELL 1924etCC1121 480V -Ell EllER SHGR Ril EL 25' R.B. EL 40' 1R24 IICC1122 480V -E11.B31.P42.T46 FE-1E 1R23eSHG-112 EttER SHGR Rtl EL 25' R.B. EL 112' 1R*4allCC1123 480V -E21.C41 EftER SHGR RH EL 25' R.B. EL 112' 12 of 13
TABIE 4.4-2 SmlTDOWN EQUIPMENT LIST . 1:24ellCC1124 480V -641 EllER SHGR RH EL 25' R.B. EL 150' . 1R24eHCC1125 480V -R42.R35.X41.X61 FE-1E 1R23eSHG-112 EllER SHGR Rtl EL 25' EllER SHGR ROOH -.
.-8 1:24etICC1124 480V -H50.P41.943.X41.X40.X41 FE-1E 1R23eSHG-112 EltER SHGR Ril EL 25' DIESEL GEN ROOH e IRZ4etICC1127 480V -E11.E21.P41 EltER SHGR RH EL 25' R.B. EL 40' 1R24atlCC1128 480V -E11.E51.P41.P42.T46 FE-1J 1R23eSHG112 EllER SHGR RH EL 25' R.B. EL 112' 1R24mitCC1129 480V -E11.P41 F E-Ill 1923eSHG112 EllER SHGR Ril EL 25' R.B. EL 40' l 1R24eTRS112f TRAt4SFER SHITCH FE-1E 1R24 ltG1138/112 R.B. EL 150'
?
1:24-HCC112A FE-1J 1R24eHCC112X R.B. EL 78' R.B. EL 78 1924-IICC112C FE-1H 1R24 flCC112X R.B. EL 78' R.B. EL 78 6 I 1:24allCC112X F E.Ill 1R23eSHG112 EllER SHGR Rig EL 25' R.B. EL 78* 1924eHCC112Y 480V -831 F E-Ill IR24eTRS112Y R.B. EL 112' R.B. EL 112' ; 1R24stlG112 IIOTOR GENERATOR FE-1E 1R23eSHG-112 EllER SHGR RH EL 25' R.B. EL 150' 1R24.PNL-01 FE-9NY 1R23elEC112Y R.B. EL 112' R.B. EL 112' , DIVISION 3 1!24 flCC1131 480V -P42.T44 FE-1E 1R23eSHG-113 EHER SHGR RH EL 25' R.B. EL 43' 1:24etICC1134 480V -tISO.P41.R43.X40. FE-1E 1R23 SilG-113 EllER SHGR Ril EL 25' DIESEL GEN ROOH I II24 tlG113A HOTOR GENERATOR FE-1E 1R24eSHG113 EltER SHGR RH EL 25' R.B. EL 150' 1R24*tIG1138 HOTOR GENERA 0TR FE-1E 1R24eSHG113 EltER SHGR Ril EL 25' R.B. EL 150' s DIVISIGH 1 II35 PtLR1 120V -itSO.R43 1R35A02 1R24mtICC1115 EllER SHGR RH EL 25' EllER SHGR ROOH EL 25 ID35eTR1 480V/120V XFIIR PtLR1 FE-1H 1R24elCC1115 EllER SHGR RH EL 25' EllER SHGR ROOH EL 25 1R35eT-R2 TRAt4SFORl!ER FE-1H 1R24ellCC1112 R.B. EL 112' R.B. EL 112 1R35mi-R3 TRANSFORitER FE-1X 1R24 tICC116 DIESEL GEN RH EL 22' DIESEL GEN ROOH EL 20 DIVISIDH 2 1R35ePILB1 120V -it50.R43 1R35B02 1R24altCC1125 EttER SHGR RH EL 25' R.B. EL 44
- 1R35eTB1 480V/120V XFist PtLB1 1R24ellCC1125 EllER SHGR RH EL 25' EttER SHGR ROOH EL 25 1R35sT-B2 TRAttSFORitER FE-1J 1R24allCC1122 R.B. EL 112' R.B. EL 1128 1R35mi-B3 TRANSFORitER FE-1X ,
IR24stICC1124 DIESEL GEH RH EL 25' DIESEL GEH ROOH DIVISION 3 1%35mT01 480V/120V XFIIR PFLO1 FE-1H 1R24ellCC1133 EllER SHGR RH EL 25' EllER SIIGR R00H EL 25 1R35ePit-01 FE-1H 1R35eT-01 EttER SHGR RH EL 25' R.B. EL 25' 1R35mT-02 TRAFISFORHER FE-1X 1R24allCC1134 DIESEL GEN RH EL 22' DIESEL GEH ROOH ; DIVISIGH L II42 0CA1 1250C- 1R42eSHGA1 BAT CH FE-1H 1R24etICC1115 EHER SHGR RH EL 25' EtIER SHGR ROOli 4 1R42ePit-Al 1250C- SHG1011111 DG FE-1AT 1R42 SHG101 EtIER SHGR RH EL 25' EllER SHGR ROOli 1R42eBAA1 125CC- 1R42eSHGA1 BAT SATT ROOli 1R42eSHGA1 1250C- PlLA11A2 EttER SHGR 90011 1R42ePNLA2 1250C- ADS SGE LOGIC EltER SHGR ROOli 1H11ePIL-VC1 125 VOC PtL FEED 11R4202 1R42ePfL-A RELAY RH EL 44' CONTROL RO0tt EL-43 1H11 Pit-VC2 125 VOC PtL FEED 11R4201 1R42ePit-A2 RELAY Ril EL 44' C0!!!ROL R00ll EL-43
- 11) THE EQUIPHEHT IN THE REACTOR BUILDIHG IS LOCATED BY ELEVATI0HIFT.) AND AZIHUTHIDEGREESit EXAIPLE- 112-230 I.E. REACTOR BUILDING. ELEVATION 112FT. ATO 230 DEGREES. Tile EQUIPilENT OUTSIDE THE RE ACTCR BUILDING IS LOCATED BY AREA. ELEVATION. LINE Ate COLulfit EXAtFLE- CB/63-C13 I.E. C0tl TROL BUILDING. ELEVATION 63FT. LINE C Ate COLutti 13.
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SHOREHAM NUCLEAR POWER STATION-UNIT 1 SEPARATION ANALYSIS REPORT
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! DEVELOPMENT OF SHUTDOWN EQUIPMENT BY AREA SHOREHAM NUCLEAR POWER STATION-UNIT I SEPARATION ANALYSIS REPORT
l 11600.02-158h 12/22/80 058 APPENDIX A 1.7 SEPARATION ANALYSIS RESULTS 1.9 PRIMARY CONTAINMENT 1.11
. 1' 11600.02-158v 12/24/80 056 SEGMENT N1 1.8 CABLE SEPARATION ANALYSIS 1.10 PRIMARY CONTAINMENT 1.11
- 1. SYSTEMS IMPACTED: 1.14 JA) Division I Systems: B21, B31, C61, E11, G33 1.16 JB) Division II Systems: B21, E41 (Division I) 1.18 JC) Division III Systems: None 1.20
- 2. SYSTEMS' FUNCTIONS DISABLED: 1.22 JA) No credit taken for Division I systems' functions, other 1.24 than the RHR (E11) and RCIC (ES1) systems.
JB) Division I RHR (E11) system shutdown cooling inboard 1.25 isolation valve 1E11*MOV047. 1.26 JC) No credit taken for Division II ADS (B21) system. 1.27 JD) No credit taken for Division II HPCI (E41) system. 1.28
- 3. DISABLED FUNCTIONS EVALUATION: 1.31 JA) Division II and III systems, and Division I RCIC system 1.33 are available for shutdown.
, JB) Division I RHR system valve 1E11*MOV047 may be manually 1.35 l operated. 1 JC) Division II ADS system is not needed since the 1 36 Division I RCIC system is available. JD) Division II HPCI system is not needed since the 1.37 1 Division I RCIC system is available. l [ 4 SHUTDOWN CAPABILITY: 1.40 Hot and cold shutdown are achievable using Division II and 1.42 III systems and the Division I RHR system with manual 1.43 operation of valve 1E11*MOV047 or the Division II RHR/CS/SRV flow path and the RCIC system. S. FURTHER ACTION RECOMMENDED: 1.47 None 1.49 l
1 l
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11t00.02-15'4 w 12/20/80 051 SEGMENT $ 1.6 CAhLE SEPARATION AhALYSIS 1.d PRIMARY CONTAINMENT 1.9 1 SYSTEMS IMPACTED: 1.12 (A) Division I Systesns: h21, 331, Co1, E11 1.14 (B) Division II Systems: B21, E41 (Div. I) 1.15 (C) Division III Systems: None 1.16
- 2. SYSTEMSe FUNCTIONS DISABLED: 1.19 JA) No credit taxen for Division I systems e Iunctions, otner 1.21 than _t,he RHR (Ell) system suutdown cooling inboard 1.2A isolation valve 1E11*MOV047 and tne RCIC (h51) system. 1.23 JB) No credit taxen for Division II ADS (b21) system. 1.24 JC) Division II HPCI (E41) systesa suppl) incoard isolation 1.25 valve 1E41*MOV041 (Division I component) 1.26
- 3. DISABLzD FUNCTION EVALUATION: 1.29 JA) Division.II and III systems, Division I RER system valve 1.31 1E11*MOV047 and RCIC systems a_re avallanle tor- snutdown. 1.32 JB) Division II ADS system is not needed since Division I 1.34 RCIC system is available.
JC) D1 vision II HPCI system valve 1h41*MOV041 may De 1.35 manually operated. ' 4 SHUTDOWN CAPABILITY: 1.38 _ Hot and cold shutdown are achievable using Division II and 1.40 III systems, Division I RER system valve lh11*MOV047 and the 1.41 RCIC system, or Division II dPCI system, 1_t manual operation 1.42 ot valve 1241*MOV041 is poss1 Die. 5, . FURTHER ACTIUh RECOMMENDED: 1.45 None 1.47 1 l 1
11600.02-158x 12/24/80 056 SEGMENT N3 1.7 CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINMENT 1.10
- 1. SYSTEMS IMPACTED: - 1.13 (A) Division I Systems: B21, B31, C61 1.15 (B) Division II Systems: B21, E41 (Div. I) 1.17 (C) Division III Systems: None 1.19
- 2. SYSTEMS' FUNCTIONS DISABLED: 1.21 No credit taken for Division I systems, other than RHR 1.25 JA)
(E11) , RCIC (E51) , and remaining ADS (B21) systems. JB) Division II ADS (B21) system valves SOVO92J and H. 1.28 Division II HPCI (E41) system s team supply inboard 1.31 JC) 1.32 isolation valve IE41*MOV041 (Division I component) .
- 3. DISABLED FUNCTION EVALUATION: 1.35 JA) Division II and III systems, Division I RBR, RCIC, and 1.38 remaining ADS systems are available for shutdown.
Division II remaining ADS system valves are available 1.41 JB) for ghutdown. 1.42-Division II HPCI system valve IE41*MOV041 may be 1.45 JC) manually operated. 4 SHUTDOWN CAPABILITY: 1.47 Hpt shutdoun is achievable using Division I RCIC System. 1.49 Cold shutdown is possible using the Division I or II RHR 1.50 systems. The Division II HPCI system could also be used for 1.52 bot shutdown, if manual operation of valve IE41*MOV041 is 1.54 possible.
- 5. FURTHER ACTION RECOMMENDED: 1.56 Npne 1.58
11600.02-158y 12/24/80 059 SBGMENT N4 1.7 ; CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINMENT 1.10
- 1. SYSTEMS IMPACTED: 1.13 JA) Division I Systems: B21, C61, E11, E51 (Div. II) 1.16 JB) Division II Systems : B21, E41 (Division I) 1.18 JC) Division III Systems: None 1.20
- 2. SYSTEMS
- FUNCTIONS DISABLED: 1.22 JA) No credit taken for Division I systems' f unctions, other 1.24 than remaining ADS (B21) system. 1.26 JB) Division I ADS (B21) system valves 1B21*SOV092AX, BX, 1.27 CX.
JC) Division II ADS (B21) system valves 1B21*SOV092AY, BY, 1.29 EY, LY. 1.30 JD) Division'II HPCI (E41) system steam supply inboard 1.31 isolation valve 1E41*MOV041. 1.32
- 3. DISABLED FUNCTION EVALUATION: 1.34 JA) Remaining Division I and II systems and Division III 1.36 l gystems are available for shutdown. 1.38 JB) Division I ADS valves 1821*SOV092AX, BX, CX are not 1.39 needed since the remaining ADS valves are adequate for 1.41 depressurization.
JC) Division II ADS valves 1B21*SOV092AY, BY, EY, LY are not 1.42 needed since the remaining ADS valves are adequate for 1.44 depressurization. JD) Division II HPCI system valve 1E41*MOV041 may be 1.45 inaccessinle with relief valve operation. 1.47 4 SHUTDOWN CAPABILITY: 1.50 Hot shutdown is achievable using the Division II RHR/CS/SRV 1.52 flow path, or the HPCI system, if manual operation of HPCI 1.54 i steam valve 1E41*MOV041 is possible. Cold shutdown is 1.55 l achievable using remaining Division II and Division III 1.56 l systems. l
11600.02-158y 12/24/d0 059 j 1 FURTHER ACTION RECOfMENDED: 2.2 None 2.4 l s
11600.02-158 z 12/23/80 058 SEGMENT jlii 1.7 CABLE SEPARATION ANALYSIS 1.9 FRIMARY CONTAINMENT 1.10
- 1. SYSTEMS IMPACTED: 1.13 (A) Division I Systems: B21, C61, G33, Ell, E51 (Div. II) 1.15 (B) Division II Systems: B21, C61 1.17 (C) Division III Systems: None 1.19
- 2. SYSTEMS
- FUNCTIONS DISABLED: 1.22 JA). No credit taken for Division I systems' functions, 1.24
.e_xcept for the RER (E11) shutdown cooling valve 1.25 1811*MOV047.
JB) Division I RHR (E11) system bypass valve 1E11*MOV081B. 1.26 JC) No credit taken for Division II ADS (B21) system. 1.27 JD) Division II remote shutdown temperature element 1.28 1C61*TE012B. 1.29
- 3. DISABLED FUNCTION EVALUATION: 1.31 JA) Division II and III systems are available zor shutdown. 1.33 JB) Division I RHR bypass valve 1E11*MOV081B is not required 1.34 for shutdown. 1.35 JC) Division II ADS system is not needed since Division II 1.36 HPCI (E41) system is available. 1.37 JD) Use of remote shutdown panel is not required for this 1.38 event.
- 4. SHDTDOWN CAPABILITY: 1.41 got and cold shutdown are achievable using Division II and 1.43 III s_ystems, and the Division I RHR system shutdown cooling 1.45 valve 1E11*MOV047. 1.46 l
S. FURTHER ACTION RECOMMENDED: 1.50 l None 1.52 bMe,M Or we m
- s.-. -, - , -_- --
11600.02-158aa 12/23/80 058 SEGMENT N6 1.7 CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINMENT 1.10
- 1. SYSTEMS DKPACTED: 1.13 JA) Division I Systems: B21, C61, G33, E11, E51 (Div. II) 1.16 JB) Division II Systems: B21, B31 1.18 JC) Division III Systems: None 1.20
- 2. SYSTEMS
- FUNCTIONS DISASLED: 1.22 JA) No credit taken for Division I systems, except RHR (E11) 1.24 and Reactor Recirculation (B31) system, and ADS (B21) 1.25 gystem valves SOV092H, J, and K. 1.26 JB) No credit taken for Division II ADS (B21) system, except 1.27 valves SOVO92C and D. 1.28 JC) Division II Reactor Recirculation (B31) system valve 1.30 1B31*MOVQ31B.
JD) Division I RER (E11) system bypass valve 1E11*MOV081B. 1.31
- 3. DISABLED FUNCTION EVALUATION: 1.33 JA) Division II and III systems and remaining Division I 1.35 systems are available for shutdown. 1.37 JB) Division II ADS system valves SOV092C and D are 1.39 available .
JC) Division II Reactor Recirculation system valve 1.40 IB31*MOV031B is not Eequired for shutdown. 1.42 JD) Division I RBR bypass valve 1E11*MOV081B is not required 1.43 for snutdown. 1.44 4 SHUTDOWN CAPABILITY: 1.47 Hot shutdown is achievable using Division II HPCI system and 1.49 cold shutdown is achievable using Division II RHR System. . 1.50 j 5. FURTHER ACTIONS RECOMMENDED: 1.53 None 1.55
~~
. ~~.
11600.02-158ab ??/24/80 055 SEGMENT Q1 1.7 CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINMENT 1.10
- 1. SYSTEMS IMPACTED: 1.13 (A) Division I Systems: B21, B31, E11, C61 1.15 (B) Division II Systems: B21, E41 (Div. I) 1.17 (C) Division III Systems: None 1.19
- 2. SYSTEMS
- FUNCTIONS DISABLED: 1.22 1A) No credit taken for Division I systems' functions, other 1.25 than the RER (E 11) and the RCIC (ESI) systems.
JB) Division I RHR (E11) system shutdown cooling inboard 1.26 isolation valve JE11*MOV047, and bypass valves 1.28 1E11*MOV081A and B. IC) No credit taken for Division II ADS (B21) system. 1.29 JD) Division'II HPCI (E41) system steam supply inboard 1.30 isolation valve JE41*MOV041 (Division I component) . 1.32
- 3. DISABLED FUNCTION EVALUATION: 1.34 JA) Remaining Division I and II systems and Division III 1.36 systems are available for shutdown. 1.37 1B) Division I RER system valve 1E11*MOV047 may be manually 1.38 operated, and valves 1E11*MOV081A and B are not required 1.39 for shutdown. 1.40 JC) Division II ADS system is not needed since Division I 1.41 RCIC a,nd Division II HPCI systems are available. 1.43 JD) Division II HPCI system valve 1E41*MOV041 may be 1.44 manually operated. 1.45 4 SHUTDOWN CAPABILITY: 1.47 Hot and cold shutdown are achievable using Division II and 1.49 III gystems, Division I RHR with manual operation of valve 1.51 1E11*MOV047 and the RCIC system, or Division II HPCI system, 1.52 if manual operation of valve 1E41*MOV041 is achievable. Cold 1.54 shutdown is also achievable using the Division II RHR/CS/SRV 1.55 flow path.
11600.02-158ab 12/24/80 933 1 FURTHER ACTION RECOMMENDED: 1.58 None 2.2 I l 1 l l l l
r 11600.02-158ac 12/24/80 055 SEGMENT 02 1.7 CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINMENT 1.10 SYSTEMS IMPACTED: 1.13 1 JA) Division I Systems: B21, B31, C61 1.16 JB) Division II Systems : B21, E41 (Div. I) 1.18 1C) Division III Systems: None 1.20
- 2. SYSTEMS ' FUNCTIONS DISABLED: 1.22 No credit taken for Division I systems' f unctions, other 1.24 JA) than the RHR (E11) and the RCIC (E51) systems. 1.27 JB) No credit taken for Division II ADS (B21) system. 1.28 JC) Division II HPCI (E41) system steam supply inboard 1.29 isolation valve JE41*MOV041 (Division I component) . 1.31
- 3. DISABLED FUNCTION EVALUATION: 1.34 JA) Remaining Division I and II systems and Division III 1.36 systems are available for shutdown. 1.37 JB) Division II ADS system is not required since Division I 1.39 RCIC and Division II HPCI systems are available. 1.41-
- JC) Division II HPCI system valve 1E41*MOV041 may be 1.42 manually operated. 1.43 4 SHUTDOWN CAPABILITY: 1.46 l
) l Hot and cold shutdown are achievable using Division II and 1.48 III systems, Division I RHR and RCIC systems, or Division II 1.50 HPCI system, if manual operation of valve 1E41*MOV041 is 1.52 possible.
- 5. FURTHER ACTION RECOMMENDED: 1.55 None 1.57
l 11600.02-158ad 12/22/80 054 SEGMENT 03 1.7 CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINMENT 1.10
- 1. SYSTEMS IMPACTED: 1.13 JA) Division I Systems: B31, C61, E11, E51 (Div. II) 1.16 JB) Division II Systems: E41 (Div. I) 1.18 JC) Division III Systems: None 1.20
- 2. SYSTEMS
- FUNCTIONS DISABLED: 1.22 JA) No credit taken f or Division I systems' f unctions, other 1.24 than the ADS (B21) system. 1.25 JB) Division II HPCI (E41) system steam supply inboard 1.26 isolation valve 1E41*MOV041. 1.27
- 3. DISABLED FUNCTION EVALUATION: 1.29 JA) Division.,II and III systems and Division I ADS system 1.31 are available for shutdown. 1.32 JB) Division II HPCI valve 1E41*MOV041 may be manually 1.33 operated, but, it may be inaccessible with HPCI steam 1.34 valve operation. However, Division II RHR/CS/SRV tiow 1.35 path is available.
4 SHUTDOWN CAPABILITY: 1.38 Hot shutdown is achievable using the Division II RER/CS/SRV 1.40 flow path, cold shutdown is achievable using remaining Division II and Division III systems. 1.41
- 5. FURTHER ACTION RECOMMENDED: 1.44 None 1.46
11600.02-158ae 12/24/80 055 SEGMENT 04 1.7 CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINME!72 1.10
- 1. SYSTEMS IMPACTED: 1.13 (A) Division I Systems: B21, C61, G33, E11, 1.15 (Division II) E51 1.16
(:B) Division II Systems : B21, C61 1.18 (C) Division III Systems: None 1.20
- 2. SYSTEMS' FUNCTIONS DISABLID: 1.22 JA) No credit taken for Division I systems' functions, 1.25 except for the RHR (E11) shutdown cooling valve 1.26 1E11*MOV047.
JB) Division I RHR (E11) system bypass valve JE11*MOV081B. 1.29 JC) No credit taken for Division II ADS (B21) system. 1.31 JD) Division'II remote shutdown temperature element 1.33 IC61*TEO22B. - 1.34
- 3. DISABLED FUNCTIONS EVALUATION: 1.37 JA) Renaining Division II and III systems are available for 1.39-shutdown. 1.40 JB) Division I RHR bypass valve 1E11*MOV081B is not required 1.44 for shutdown.
JC) Division II ADS system is not required since the 1.46 Division II EPCI system is available. 1.47 JC) Use of remote shutdown panel is not required for this 1.49 event. 1.50 4 SHUTDOWN CAPABILITY: 1.52 l Hot shutdown is achievable using Division II HPCI system. 1.55 Cpid shutdown is achievable using remaining Division II and 1.56 Division III systems, and the Division I RHR system shutdown 1.57 cooling valve 1E11*MOV047.
- 5. FURTHER ACTION RECOMMENDED: 2.2 Npne 2.4 1
11600.02-158af 12/24/80 055 SEGMENT 05 1.7 CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINMENT 1.10
- 1. SYSTEMS IMPACTED: 1.13 (A) Division I Systems: B21, C61, E11, G33, E51 (Div. II) 1.15 (B) Division II Systems: B21, B31, C61 1.17 (C) Division III Systems: None 1.19
- 2. SYSTEMS
- FUNCTIONS DISABLED: 1.22 JA) No credit taken for Division I systems other than 1.24 Reactor Recirculation (B31) and RER (E11) systems, and ADS JB21) system valves SOV092C and D. 1.25 JB) No credit taken for Division II ADS (B21) system other 1.26 than valves SOV092H, J, and K.
JC) Division II Reactor Recirculation (B31) system valve 1.27 1831 *MOV O,31B. JD) Division II Remote Shutdown (C61) system temperature 1.28 element 1C61*TE022B. (E) Division I RHR (E11) system bypass valve 1E11*MOV081B. 1.29
- 3. DISABLED FUNCTIONS EVALUATION: 1.32 JA) Division II and III systems and remaining Division I 1.34 systems are available for shutdown.
JB) Division II ADS system valves SOV092H, J, and.K are 1.35 available. JC) Division II Reactor Recirculation system valve 1.37 1B31*MOV031B is not required for shutdown. JD) Use of remote shutdown panel is not required for this 1.38 event. JE) Division I RHR bypass valve 1E11*MOV081B is not needed. 1.39 4 SHUTDOWN CAPABILITY: 1.42 Hot shutdown is achievable using Division II HPCI system, and 1.44 cold shutdown is achievable using Division I and Division II 1.45 RHR/CS/SRV flow paths. i i t
11600.02-158af 12/24/80 055 1 FURTHER ACTION RECOMMENDED- 1.48 None 1.50 l
. _ _ . _ _ l
. ~'..
11600.02-158ag 12/23/80 051 SEGMENT 0.6_ 1.7 CABLE SEPARATION ANALYSIS 1.9 PRIMARY CONTAINMENT 1.10
,1. SYSTEMS IMPACTED: 1.13 (A) Division I Systems: B21, C61, E11, G33 . 1.15 (B) Division II Systems: B21, B31 1.17 (C) Division III Systems: None 1.19
- 2. SYSTEMS
- FUNCTIONS DISABLED: 1.22 JA) No credit taken for Division I systems' functions except 1.24 Reactor Recirculation (B31) , RER (E11) and RCIC (E51) 1.25 systems.
JB) No credit taken for Division II ADS (B21) system. 1.26 JC) Division II Reactor Recirculation (B31) system valve 1.27 1B31*MOV031B. JD) Division'I RHR (E11) system valves 1E11*MOV047 and 1.28 1E11*MOV081B.
- 3. DISABLED FUNCTION EVALUATION: 1.30 JA) Remaining Division I and II systems and Division III 1.32 systems a_re available for shutdown. 1.33 JB) Division II ADS system is not required since Division II 1.34 HPCI and Division I RCIC _ systems are available for hot 1.35 shutdown, and Division I ADS is available for the Division II RER/CS/SRV flow path.
JC) Division II Reactor Recirculation system valve is not 1.36 required. JD) Division I RHR shutdown cooling valve 1E11*MOV047 may be 1.37 manually operated, and bypass valve 1E11*MOV001B is not 1.38 required for shutdown. 4 SHUTDOWN CAPABILITY: 1.41
.H_ot shutdown is achievable using Division I RCIC or Division 1.43 II HPCI system. Cold shutdown is achievable using Division I 1.44 ADS valves and Division II RHR/CS/SRV flow path. 1.45
- 5. FURTHER ACTION RECOMMENDED: 1.48
_None 1.50
. v.
11600.02-158u 12/24/80 051 APPENDIX B 1.5 SEPARATION ANALYSIS RESULTS 1.7 SECONDARY CONTAINMENT 1.9 G 5' . l
. ,0 11600.02-158o 12/24/80 059 SEGMENT 008-N1 1.6 SEPARATION ANALYSIS 1.7 SECONDARY CONTAINMENT 1.8
- 1. SYSTEMS IMPACTED: 1.11 (A). Division 1 System: E11, P41, P42, T46 1.13 (B) Division II Systems: P41 1.15 (C) Division III Systems: None 1.17
- 2. SYSTEMS' FUNCTIONS DISABLED: 1.19 JA) No credit taken for Division I systems' functions, 1.22 other than the RHR (E11) system shutdown cooling 1.23 inboard isolation valve 1E11*MOV047. 1.24 JB) Division II SW (P41) system fuel pool drain valve 1.27 1P41*MOV043.
JC) Division I and II SW (P41) system drain valves 1.29 1P41*MOV039A,B. 1.30 JD) Division I and II SW (P41) systems ultimate gooling 1.33 valves'1P41*MOV033A,B, C, D.
- 3. DISABLED FUNCTION EVALUATIONS: 1.35 JA) Division II and III systems are available. 1.37 JB) Fuel pool cooling can be ef f ected by intermittent use 1.40 of Division II RHR system.
JC) Division I and II SW systems drain valves are not 1.42 required since Division II RHR system is available. 1.44 JD) Division I and II SW system ultimate cooling valves 1.47 are not necessary since Division II RHR system is 1.48 available. 4 SHUTDOWN CAPABILITY: 1.50 Hot and cold shutdown are achievable using Division II and 1.53 III systems.
- 5. FURTHER ACTION RECOMMENDED: 1.55 None 1.57
11600.02-158o 12/24/80 059 SEGMENT 000-N2 2.2 SEPARATION ANALYSIS 2.3 SECONDARY CONTAINMENT 2.4
- 1. SYSTEMS IMPACTED: 2.7 (A) Division I Systems : Ell, E21, P41, P42, T46 2.9 (B) Division II Systems : None 2.11 (C) Division III Systems: E11 (C) 2.13
- 2. SYSTEMS' FUNCTIONS DISABLED: 2.16 No credit taken for Division I and III (C) systemse 2.18
.f_ unctions, other than the RHR (E11) system shutdown cooling 2.19 inboard isolation valve 1E11*MOV047.
- 3. DISA3 LED FUNCTION EVALUATION: 2.21 Division II and III (D) systems are available. 2.23 4 SHUTDOWN CAPABILITY: 2.25 Hot and col'd shutdown are achievable using Division II and 2.27 III (D) systems. 2.28
- 5. FURTHER ACTION RECOMMENDED: 2.31 None 2.33
11600.02-158o 12/24/80 059 SEGMENT 008-N3 2.37 SEPARATION ANALYSIS 2.38 SECONDARY CONTAINMENT 2.39
- 1. SYSTEMS IMPACTED: 2.42 (A) Division I Systems: B21, B31, C41, E11, E21, E51, 2.44 G33, G41, P41, P42, T46, Z93 2.45 (lB) Division II Systems: E41 (Div. I components only) 2.47 (C) Division III Systems: None 2.49
- 2. SYSTEMS ' FUNCTIONS DISABLED: 2.51 JA) No credit taken for Division I systems' functions. 2.54 JB) Division II HPCI (E41) system will not tolerate 2.56 spurious. action of its Division I components. These 2.58 include pressure switches which are connected locally either in parallel or in series and run back to the R11-P617 panel as a single wire pair (1E41*PS025ASC, 3.1 1E41*PS023ASC, and 1E41*PDS022A).
JC) RHR (211) system shutdown cooling inboard isolation 3.3 valve 1E11*MOV047 3.4
- 3. DISABLED FUNCTION EVALUATION: 3.6 l JA) Division II and III systems are available. 3.8 JB) Division II RHR/CS/SRV flow path is available. 3.10 1C) RHR system valve 1E11*MOV047 can be manually operated. 3.12 4 SHUTDOWN CAPABILITY: 3.14 Rot shutdown is achievable using Division II RHR/CS/SRV flow 3.16 Eath. 3.17 Cold shutdown is achievable using Division II RHR with 3.19 manual operation of valve 1E11*MOV047, or Division II 3.20 RHR/CS/SRV circulation / suppression pool cooling mode.
I,n some instances the HPCI System could be used for hot 3.22 shutdown if the following cables are protected: 3.23 1E41 ARC 404 3.26 l 1E41 ARC 405 3.27 1E41 ARC 408 3.28 l l - .-.
11600.02-138o 12/24/80 059 5_ . , FURTHER ACTION RECOMMENDED: 3.32 Separate the " red" cables associated with the HPCI pressure 3.34 switches 1E41*PS022ASC, 1E41*P5023A and 1E41*PDS025ASC, from 3.35 the RCIC " red" cables so that HPCI may be available for hot 3.36 shutdown. Alternatively, protect the affected raceways using thermal 3.40 barriers such as Kaowool blankets.
- 6. ACTION TO BE TAKEN 3.42 Affected conduits will be protected by thermal barriers 3.44 JKaowool blankets). 3.45 e
i { l m.. _, _ _ _ - .
11600.02-158o 12/24/80 059 SEGMENT 008-N4 3.48 SEPARATION ANALYSIS 3.49 SECONDARY CONTAINMENT 3.50
- 1. SYSTEMS IMPACTED: 3.53 (A) Division I Systems: B21, C61, E11, E21, E51, Z93 3.55 (B) Division II Systems: E41 (including Div. I 3.57 components) 3.58 (C) Division III Systems: E11 (C) , P42 (C) , T46 4.2
- 2. SYSTEMS ' FUNCTIONS DISABLED: 4.4 JA) No credit taken for Division I or III systems' 4.7 f_ unctions, other than the RHR (E11) system p_hutdown 4.9 cooling inboard isolation valve 1E11*MOV047. 4.10 JB) No credit taken for Division II RPCI (E41) systems' 4.12 functions. 4.13
- 3. DISABLED FUNCTION EVALUATION: 4.15 Division II RER/CS/PRV flow path is available. 4.17 4 SHUTDOWN CAPABILITY: , 4.20 got shutdown is achievable using Division I and II 4.23 RHR/CS/SRV flow path. ,
4.24-
.I_n some instances the HPCI system could be used for hot 4.27 shutdown if the following cables are protected. 4.28 1E41ARX449 4.31 1E41ARX450 4.32 1E41ARX451 4.33 1E41ARX452 4.34 Cold shutdown is achievable using Division II normal RHR. 4.36 l
- 5. FURTHER ACTION RECOMMENDED: 4.39 Separate the " red" cables associated with the HPCI 4.41 temperature elements 1E41*TE054 and 1E41*TE055 from the RCIC 4.42
" red" cables so that HPCI may be available for hot shutdown. 4.43 Alternatively, protect the affected raceways using thermal 4.45 barriers such as Kaowool blankets. 4.46 Also the reduction of fire hazard in the vicinity of the 4.48 HPCI a_nd RCIC pumps and surrounding raceways may make 4.49 available the RCIC or HPCI systems as alternative to using l the RHR/CS/SR*.' ff.ow path. 4.50
11600.02-158o 12/24/80 059
- 6. ACTION TO BE TAKEN 4.52 Affected conduits will be protected by tnermal barriers 4.54 JKaowool blankets). u.55 To reduce the fire hazard in the HPCI/RCIC area, the 4.57 following will be provided: 4.58 JA) Additional water spray, cable tray bottoms on selected 5.2 horizontal " Red" trays, and thermal barrier (Kaowool 5.3 blankets) on selected " Red" conduits.
JB) Curbs around the HPCI and RCIC turbines. 5.5 JC) Additional local smoke detection. 5.7 JD) A partial fire barrier between vertical cable trays 5.9 and the adjacent RCIC turbine. 5.10 4
-- ~
^
l 11 BOO.02-158o 12/24/30 059 SEGNENT 008-N5 5.13 SEPARATION ANALYSIS 5.14 SECONDARY CONTAINMENT 5.15
- 1. SYSTEMS IMPACTED: 5.18 (A) Division I Systems: B21, E51 (including Div. II 5.20 components) 5.21 (B) Division II Systems: B21, B31, C41, C61, E11, E21, 5.23 E41 (including Division I 5.24 components) , G33, G41, P41, 5.25 P42, T46, Z93 5.26 (C) Division III Systems: C61, P41, P42, T46 5.28
- 2. SYSTEMS
- FUNCTIONS DISABLED: 5.30 JA) No credit taken for Division II and III systems' 5.33
.f_ unctions, other than the RER (E11) system shutdown 5.34 cooling outboard isolation valve 1E11*MOV048.
JB) Reactor low water level switch 1B21*L1SO27C only 5.36 impacts Division I RCIC (E51) and RHR (E11) systems. 5.37 JC) No credit taken for Division I RCIC (E51) system. 5.39
- 3. DISABLED FUNCTION EVALUATION: 5.41 1A) Division I RHR/CS/SRV flow path is available. 5.43 JB) Reactor low water level switch 1B21*L1SO27C is one out 5.45 of two Division I sensors, and the redundant unit 5.46 1B21*L1SO27A remains functional. 5.47 1 SHUTDOWN CAPABILITY: 5 49 Hot shutdown is achievable using Division I RER/CS/SRV flow 5.51 path with a manual pressure reduction and Division I CS 5.52 system (E21) providing makeup.
In some instances the HPCI or RCIC systems could be used for 5.54 hot shutdown if the following cables are protected: 5.55 (a) 1E41 ARC 405 (b) 1E51BBC310 5.58 1E41ARX449 1E51BBX431 6.1 1E41ARX450 1E51BBX432 6.2 1E41ARX451 1E51BBX433 6.3 ,
. 1E41ARX452 1E51BBX434 6.4 Cold shutdown is achievable using Division I RHR system. 6.6
11600.02-158o 12/24/80 059
- 5. FURTHER ACTION RECOMMENDED: 6.10 Separate the " red" cables under 4 (a) above associated with 6.12 the HPCI pressure switches 1E41*PS025A and C and temperature 6.13 elements 1E41*TE054A and 1E41*TE055A from the RCIC " red" 6.14 cables so that HPCI may be available for hot shutdown.
Also, separate the " blue" cables under item 4 (b) above 6.18 associated with the RCIC pressure switches 1E51*PS025B and D and temperature elements 1E51*TE053B and 1E51*TE054B from 6.19 the HPIC
- blue" cables so that RCIC may be available for hot shutdown.
In addition the reduction of fire hazard in the vicinity of 6.21 the HPCI and RCIC pumps and surrounding raceways may make 6.22 availabl'e the RCIC cr HPCI systems as alternative to using the RHR/CS/SRV flow path. 6.23 Alternatively, protect the effected raceways using thermal 6.26 barriers such as Kaowool blanXets. A. ACTION TO BE TAKEN 6.28 Affected conduits will be protected by thermal barriers 6.30 JKaowool blan.kets). 6.31 To reduce the fire hazard in the HPCI/RCIC area, the 6.33 following will be provided: 6.34 1A) Additional water spray, cable tray bottoms on selected 6.36 horizontal " Red" trays, and thermal barrier (Kaowool 6.37 blankets) on selected " Red" conduits. IB) Curbs around the HPCI and RCIC turbines. 6.39 JC) Additional local smoke detection. 6.41 JD) A partial fire barrier between vertical cable trays 6.43 and the adjacent RCIC turbine. 6.44 l I 1 l l l
I I I 11600.02-158o 12/24/80 059 SEGMENT 008-N6 6.47 SEPARATION ANALYSIS 6.48 SECONDARY CONTAINMENT 6.49
- 1. SYSTEMS IMPACTED: 6.52 (A) Division I Systems: E51 (including Div. II 6.54 components) 6.55 (B) Division II Systems: B21, B31, C41, C61, E11, E21, 6 57 E41, G33, G41, P41, P42, T46, 6.58 Z93 7.1 (C) Division III Systems: E11 (D) 7.3
- 2. SYSTEMS
- FUNCTIONS DISABLED: 7.5 JA) No credit taken for Division I RCIC (E51) systems' 7.8 functions. 79 JB) No credit taken for Division II systems' functions. 7.11 JC) No credit taken for Division III RHR (E11) (D) system 7.13 functio,ns. 7.14 JD) RER (Ell) system shutdown cooling outboard isolation 7.16 valve 1E11*MOV048. 7.17
- 3. DISABLED FUNCTION EVALUATION: 7.20 JA) RHR system vaive 1E11*MOV047 can by manually operated. 7.22 JB) Division I RHR/CS/SRV flow path is available. 7.25
- 4. SHUTDOWN CAPABILITY: 7.27 H_ot shutdown is achievable using Division I RHR/CS/SRV flow 7.29 path with a manual pressure reduction a_nd Division I CS 7.30 system (E21) providing makeup.
In some instances the RCIC system could be used for hot 7.33 shutdown if the following cables are protected: 1E51BBC310 - 7.36 1E51BBC320 7.37 1E51BBC322 7.38 Cold shutdown is achievable using Division I RER system 1 7.41 with manual operation of valve 1E11*MOV048, or Division I 7.42 RHR/CS/SRV circulatory / suppression pool cooling modes.
l i
. *. \
i 11600.02-158o 12/24/80 059
- 5. FURTHER ACTION RECOMMENDED: 7.45 Separate the " blue" gables associated with the RCIC pressure 7.48 switches 1E51*PS022B, 1E51*PS023B and D, and 1E51*P5025B and D from the " blue" HPCI cables, so that RCIC may be available 7.49 for hot shutdown.
Alternatively, protect the a,ffected raceways using thermal 7.53 barriers such as Kaowool blankets.
- 6. ACTION TO BE TAKEN 7.55 Affected conduits will be protected by thermal barriers 7.57 1Kaowool blankets). 7.58 b
11600.02-158o 12/24/80 059 SEGMENT 008-N7 8.3 SEPARATION ANALYSIS 8.4 SECONDARY CONTAIMMENT 8.5
- 1. SYSTEMS IMPACTED: 8.8 (A) Division I Systems: None 8.10 (B) Division II Systems: B21, C61, E11, E21, P41, P42, 8.12 Z93 8.13 (C) Division III Systems: E11 (D) 8.15
- 2. SYSTEMS' FUNCTIONS DISABLED: 8.17 JA) No credit taken for Division II systems' functions, 8.20
,o_ther than the RER (E11) system shutdown cooling 8.21 outboard isolation valve 1E11*MOV048.
JB) No credit taken for Division III (D) systems' 8.23 functions. 8.24
- 3. DISABLED FUNCTION EVALUATION: 8 26 Division I and III(C) systems are available. 8.28 4 SHUTDOWN CAPABILITY: 8.31 Hot and cold shutdown are achievable using Division I and 8.33 III (C) systems. 8.34
- 5. FURTHER ACTION RECOMMENDED: 8.37 None 8.39 l
l
. ca 11600.02-158o 12/24/80 059 SEGMENT 008-N8 8.42 SEPARATION ANALYSIS 8.43 SECONDARY CONTAINMENT 8.44
- 1. SYSTEMS IMPACTED: 8.47 (A) Division I Systems: P41, P42, T4 6 8.49
(:B) Division II Systems: B21, C61, E11, E41, P41, P42, 8.51 Z93 8.52 (C) Division III Systems: None 8.54
- 2. SYSTEMS
- FUNCTIONS DISABLED: 8.56 JA) No credit taken for Division II-systems' functions, 9.1 other than RHR (E11) system shutdown cooling outboard 92 1 solation valve 1E11*MOV048.
JB) Division I SW (P41) and RBCLCW (P42) system affected 9.4 components result in the loss of Division I RBCLCW 9.5 system. JC) Division I RBSVS (T46) system unit cooler 1T46*UC002A. 9.8
- 3. DISABLED FUNCTION EVALUATION: 9.11 1A) Division I and III systems are available. 9.13 JB) Division I RHR system shutdown cooling mode using the 9.16' Division II RBCLCW system is unavailable; however, the 9.17 Division I RHR/CS/SRV flow path is available.
JC) Division I RBSVS unit cooler 1T46*UC002A impacts 9.19 Division II equipment. 9.20 4 SHUTDOWN CAPABILITY: 9.22 Hot shutdown is achievable using Division I RCIC system. 9.24 Cold shutdown is achievable using Division I RHR/CS/SRV flow 9.26 Eath. 9.27
- 5. FURTHER ACTION RECOMMENDED: 9.29 N,one 9.31
l 11600.02-1581 12/24/80 051 , SEGMENT 008-01 1.5 SEP?. RATION ANALYSIS 1.6 SECONDARY CONTAINMENT 1.7 I l
- 1. SYSTEMS IMPACTED: 1.10 1
(A) Division I Systems: E11, P41, P42, T46 1.12 (B) Division II System: P41 1.14 (C) Division III Systems: None 1.16
- 2. SYSTEMS
- FUNCTIONS DISABLED: 1.19 JA) No credit taken for Division I system functions, gther 1.22 than the RER (E11) system shutdown cooling inboard isolation valve 1E11*MOV047.
JB) Division II S,W (P41) system fuel pool drain valve 1.25 1P41*MOV043. JC) Divisions I and II SW (P41) system drain galves 1.28 1P41*MOV03A and B. JD) Divisions I and II SW (P41) systems ultimate cooling 1.30 galves 1P41*MOV033A, B, C, and D. 1 31
- 3. DISABLED FUNCTION EVALUATION: 1.34 JA) Division II and III systems are available. 1.3 b '
l JB) Fuel pool cooling can be eff ected by intermittent use 1.39 l r of Division II RHR (E11) system, instead of the SW 1.40 system. JC) Divisions I and II SW system drain valves not 1.43 necessary since Division II RHR system is available. 1.44 JD) Divisions I and II SW system supply valves are not 1.46 necessary since Division II RHR system is available. 1.48 4 SHUTDOWN CAPABILITY: 1.50 Hot and cold shutdown are achievable using Division II 1.52 l and III systems. 1.53 l S. FURTHER ACTION RECOMMENDED: 1.55 l None 1.57 l l
. to 11600.02-1581 12/24/80 051 SEGMENT 008-02 2.2 SEPARATION ANALYSIS 2.3 SECONDARY CONTAINMENT 2.4 1
- 1. SYSTEMS IMPACTED: 2.7 )
(A) Division I Systems: Ell, E21, P41, P42, T46 2.9 (B) Division II Systems: None 2.11 (C) Division III System: E11 (C) 2.13
- 2. SYSTEMS' FUNCTIONS DISABLED: 2.16 No credit taken for Division I and III(C) systems functions, 2.19 other than RER (E11) system shutdown cooling inboard isolation valve 1E11*MOV047.
- 3. DISABLED FUNCTION EVALUATION: 2.21 Division II and III (D) systems are available. 2.23 4 SHUTDOWN CAPABILITY: 2.25 got and col'd shutdown are achievable using Division II and 2.28 III (D) systems.
- 5. FURTHER ACTION RECOMMENDED: 2.31 None 2.33 t
l
. I e 4o t l 11690.02-1581 12/24/80 051 SEGMENT 008-03 2.37 SEPARATION ANALYSIS 2.38 SECONDARY CONTAINMENT 2.39
- 1. SYSTEMS IMPACTED: 2.42 (A) Division I Systems: B21, B31, C41, E11, E21, E51, 2.44 G33, G41, P41, P42, T46, Z93 2.45
(.B ) Division II Systems: E41 (Div. I components only) 2.47 (C) Division III System: E11 (C) 2.49
- 2. SYSTEMS ' FUNCTIONS DISABLED: 2.51 JA) No credit taken for Division I and III (C) systems' 2.54 functions. 2.55 JB) Division II HPCI (E41) system will not tolerate 2.57 spurious actions of its Division I components. These 2.58 include valve 1E41*MOV041 and pressure and level switches. These switches are either in parallel or 3.1 series connected locally and run back to the H11-P617 3.2 panel as a single wire pair. 3.3 JC) RHR (E 11) system shutdown cooling inboard isolation 3.5 valve 1E11*MOV047. 3.6
- 3. DISABLED FUNCTION EVALUATION: 3.8 1A) Division II systems are available. 3.10 JB) HPCI system valve 1E41*MOV041 will have to De manually 3.12 operated. Eield inspection indicated that it is not 3.13 possible to relocate the valve cable 1E41NRC146 away from this segment so a,a to maintain remote valve 3.14 operation. Division II is available. 3.15 1C) RHR system valve 1E11*MOV047 can be manually operated. 3.17 4 SHUTDOWN CAPABILITY: 3.19 Hot shutdown is achievable using Division II and III JD) 3.22 RER/CS/SRV flow path.
~
11600.02-1581 12/24/80 051 In some instances the HPCI system could be used f or hot 3.26 snutdown, if the following cables are protected: 1E41 ARC 404 3.29 1E41 ARC 405 3.30 1E41 ARC 408 3.31 Cold shutdown is achievable using Division II RHR with 3.34 manual 2Peration of valve 1E11*MOV048, or Division II and 3.35 III JD) RHR/CS/SRV c_irculator/ suppression pool cooling flow 3.37 path.
- 5. FURTHER ACTION RECOMMENDED: 3.39 Separate the " red" cables associated with the HPCI pressure 3.41 switches 1E41*PS023A and C, 1E41*PS025A and C, and 1E41*PDS022A from the " red" RCIC cables, so that BPCI may be 3.43 available for hot shutdown. Alternatively, protect the 3.44 affected raceways using thermal barriers such as Kaowool 3.45 blankets.
- 6. ACTION TO BE TAKEN 3.47 Affected conduits will be protected by thermal barriers 3.49 JKaowool Blankets). 3.50
/
'. s ..
11600.02-1581 12/24/80 051 SEGMENT 008-04 3.53 SEPARATION ANALYSIS 3.54 SECONDARY COM'AIMENT 3.55
- 1. SYSTEMS IMPACTED: 3.58 (A) Division I System: E51 4.2
(:B) Division II System: E41 (including Div. I 4.4 components) 4.5 (C) Division III Systems: None 4.7
- 2. SYSTEMS
- FUNCTIONS DISAhLED: 4.10 JA) No credit taken for Division I RCIC (E51) system 4.12 functions. 4.13 1B) No credit taken for Division II HPCI (E41) system 4.15 functions. 4.16
- 3. DISABLED FUNCTION EVALUATION: 4.18 Divisions I and II RHR/CS/SRV flow paths are available. 4.21 4 SHUTDOWN CAPABILITY: 4.24 Hot shutdown is achievable using the Divisions I and II 4.26 RHR/CS/SRV flow path with a manual pressure reduction and 4.28 Division I or II CS systems (E21) providing makeup.
l In some instances the HPCI system could'be used for hot 4.32 shutdown if the following cables are protected: 1E41 ARC 405 4.35 l 1E41ARX450 4.36 1R41ARX451 4.37 l 1E41ARX452 4.38 Cold shutdown is achievable using Division I or II EHR 4.42 l system.
- 5. FURTHER ACTION RECOMMENDED: 4.44 Separate the " red" cables associated with the HPCI pressure 4.47 switches 1E41*PS025A and C and temperature elements 1E41-TE054A and 1E41-TE055A from the " red" RCIC caDies, so that 4.48 HPCI may be available for hot shutdown.
i Alternatively, protect the affected raceways using thermal 4.51 bariers such as Kaowool blankets. l In addition, the reduction of fire hazard in the vicinity of 4.53 the RPCI a_nd RCIC pumps and surrounding raceways may make 4.55
'. v. 11600.02-1581 12/24/80 051 available the RCIC or HPCI system as alternative to using 4.57 the RER/CS/SRV flow path.
- 6. ACTION TO BE TAKEN 5.2 Affected conduits will be protected by thermal barriers 5.4 JKaowool Blankets). 5.5 To reduce the fire hazard in the BPCI/RCIC area, the 5.8 following will be provided: 5.9 JA) Additional water spray, cable tray bottoms on selected 5.11 horizontal " Red" trays, and thermal barrier (Kaowool 5.12 Blankets) on selected " Red" conduits. 5.13 JB) Curbs around the HPCI and RCIC turbines. 5.15 JC) Additional local smoke detection 5.18 JD) A partial fire barrier between vertical cable trays 5.20 and the adjacent RCIC turbine. 5.22
11600.02-158i 12/24/80 051 SEGMENT 008-05 5.25 SEPARATION ANALYSIS 5.26 SECONDARY CONTAINMENT 5.27
- 1. SYSTEMS IMPACTED: 5.30 (A) Division I System: E51 (including Div. II 5.32 components) 5.33
(:B) Division II Systems: B21, B31, C41, C61, E11, E21, 5.35 E41 (including Division I 5.36 compon ents) , G33, G41, P41, P42, 5.37 T46, Z93 5.38 (Q Division III Systems: E11 (D) , C61 (D) , P41 (D) , P42 (C) , 5.40 T46 5.41
- 2. SYSTEMS
- FUNCTIONS DISABLED: 5.44 JA) No credit taken for Division I RCIC (E51) system 5.46 tunctions. 5.47 JB) No credit taken for Division II system functions. 5.49 JC) No credit taken for Division III system functions. 5.51 JD) RHR (E11) system shutdown cooling outboard isolation 5.53 valve 1E11*MOV048. 5.54
- 3. DISABLED FUNCTION EVALUATION: 5.56 1A) RHR system valve 1E11*MOV047 can be manually operated. 5.58 JB) Division I RHR/CS/SRV flow path is available. 6.2 4 SHUTDOWN CAPABILITY: 6.4 H_ot shutdown is achievable using the Division I RHR/CS/SRV 6.6 11ow path with a manual pressure reduction and Division I CS 6.8 system (E21) providing makeup.
In some instances the HPCI or RCIC systems could be used for 6.10 hot shutdown if the following cables are protected: 6.11 (a) 1E41ARX449 (b) 1E51BBC310 6.14 1E41ARX450 1E51BBC320 6.15 1E41ARX451 1E51BBC422 6.16 1E41ARX452 1E51BBX431 6.17 1E51BBX432 6.18 1E51BBX433 6.19 1E51BBX434 6.20
11600.02-1581 12/24/80 051 C_old shutdown is achievable using the normal RHR system with 6.24 manual operation of valve 1E11*MOV048, or Division 1 6.25 RHR/CS/SRV circulation / suppression pool cooling flow path. 6.26 5, . FURTHER ACTION RECOMMENDED: 6.28 Separate the " red" HPCI cables under Item 4 (a) above 6.30 associated with temperature elements 1E41*TE054A and 6.31 1E41*TE055A from the RCIC " red" cables so that HPCI may be a_vailable for hot shutdown. 6.32 Also, separate the " blue" RCIC cables under Item 4 (b) above 6.35 associated with pressure switches 1E51*PS022B, 1E41*PS023B and D and 1E51*PS025B a_nd D, and temperature elements 6.36 1E51*TE053B and 1E51*TE054B from the HPCI " blue" cables so that RCIC may be available for hot shutdown. 6.37 A_1ternatively, protect the affected .r_aceways using thermal 6.40 barriers such as Kaowool blankets. 6_ . ACTION TO BE TAKEN 6.43 Affected conduits will be protected by thermal barriers 6.45 JKaowool Blankets). 6.46 O g= -. - = .
- - - - - - - -- e v- - - - - ,--- , . - -
e g* e, > 11600.02-1581 12/24/80 051 SEGMENT 008-06 6.51 SEPARATION ANALYSIS 6.52 SECONDARY CO?FPAINMENT 6.53
- 1. SYSTEMS IMPACTED: 6.56 (A) Division I System: None 6.58 (B) Division II Systems: B21, C41, C61, Ell, E21, E41, 7.2 Gu1, P41, P42, T46, Z93 7.3 (C) Division III System: E11 (D) 7.5
- 2. SYSTEMS' FUNCTIONS DISABLED: 7.8 JA) No credit taken for Division II system functions, 7.10
_other than RBR (Ell) system shutdown cooling outboard 7.11 isolation valve 1E11*MOV048. JB) No credit taken for Division III(D) system functions. 7.14
- 3. DISABLED FUNCTION EVALUATION: 7.16 Divisions I and III(C) systems are available. 7.18 4 SHUTDOWN CAPABILITY: 7.21 Hot and cold shutdown are achievable using Divisions I and 7.23 III JC) systems. 7.25
- 5. FURTHER ACTION RECOMMENDED: 7.28 None 7.30 l
- l. -_ - _ _ _ _ -- _ . _ _ __. - _ _ _ _ _ _ _ _ - - - - . . . _ _ __ _ _ .
.- gs 3
11600.02-1581 12/24/80 051 SEGMENT 008-07 7.33 SLPARATION ANALYSIS 7.34 SECONDARY CONTAINMENT 7.35
- 1. SYSTEMS IMPACTED: 7.38 (A) Division I Systems: P41, T46 7.40 I
(B) Division II Systems: E11, E41, P41, P42, T46, Z93 7.42 (C) Division III Systems: None 7.44
- 2. SYSTEMS
- FUNCTIONS DISABLED: 7.47 1A) No credit taken for Division II system functions, 7.49 other than RER (E11) system shutdown cooling outboard 7.50 isolation valve 1E11HOV048.
IB) Division I SW (P41) system affected components result 7.52 in the loss of D_ivision I RBCLCW (P42) system. 7.53 JC) Division I RBSVS (T46) system unit cooler 1T46*UC002A. 7.55
- 3. DISABLED FUNCTION EVALDATION: 7.58 JA) Division I and III systems are available. 8.3 JB) Division I RBR (E11) system shutdown cooling mode 8.6 using the .D_ivision II RBCLCW system is unavailable; 8.8 however, the RHR/CS/SRV flow path is availacle. 8.9 1C) Division I RBSVS system unit cooler 1T46*DC002A 8.11 impacts D_ivision II equipment. 8.12 4_ . SHUTDOWN CAPABILITY: 8.14 l
got shutdown is achievable using Division I RCI'C system. 8.16 C_old shutdown is achievable using Division I RHR/CS/SRV flow 8.18 Eath. 8.19
- 5. FURTHER ACTION RECOMMENDED: 8.21 None 8.23
t ..
< ' ', c 11600.02-1581 12/24/80 051
, SEGMENT 008-08 8.26 .24 SEPARATION ANALYSIS 8.27 SECONDARY CONTAINMENT 8.28 .27
- 1. SYSTEMS IMPACTED: 8.31
.29 (A) Division I Systems: Ell, P41, P42, T46 8.33 .30
.32 (B) Division II Systems: E11, P41, P42 8.35 (C) Division III Systems: None 8.37 .36
- 2. SYSTEMS' FDNCTIONS DISABLED: 8.40 .39 1A) Divisions I and .II RHR (E11) system heat exchanger 8.42 inlet valves lE11*MOV033A and B. 8.43 JB) Direct cooling of fuel pool by both Division I and II 8.45 of SW (P41) systems. 8.46 1C) RHR (E11) system emergency cooling backup from SW 8.48 (P41) system for both Divisions I and II. 8.49 JD) Ultimate cooling supply valves 1P41*MOV033A,B,C, and 8.51 D) of Divis, ions I and II SW (P41) systems. 8.52 JE) SW (P41) and RBCLCW (P4 2) systems' sides of the RBCLCW 8.54 system heat exchangers for both Divisions I and II. 8.55 JF) Division I RBSVS (T46) system unit cooler 1T46*UC002A. 8.58
- 3. DISABLED FUNCTION EVALUATION: 9.3 JA) Divisions I and II RHR system heat exchanger inlet 9.5 valves 1E11*MOV033A and B are physically located 9.6 outside this segment and could be manually operated in order to use the RHR system heat exchangers.
IB) Fuel pool cooling can be effected by intermittent use 9.8 of Division I ,R_HR system. 9.9 JC) SW ultimate cooling not required for shutdown 9.11 l JD) Cross-connection of Divisions I and II of SW systems 9.13 is not necessary since both the SW divisions are 9.14 s,eparately available. JE) Division I RER shutdown cooling modes are unavailable; 9.16 however, Division I and II RHR/CS/SRV flow paths are 9.17 available. 9.18 JF) Division I RBSVS system unit cooler 1T46*VC002A 9.20 impacts Division II e_quipment. 9.21 __,.r_ _ . _ . _ _ _ _ _ _ .. _ _ _, _ _ _ _
11600.02-1581 12/24/00 051.:
'. , .h .
- i. SNUTDowts.CAPAB ETTY: pd Hot shutdown is achierable using tha pivision I HPCI or AN.; -
N' Division II RCIC syste:a. Cold shutdown is achievabic using Divisions I and II 9.; BBR/CS/SRV flow paths with tlwa P.na system used in- 9.: suppression Rool _coolin9, and wtausi operation of valves. 9, . : 1E11*MOV33A and B.
- u
. Y
- J
),. FOR'11tER ACTIOtt RECOMElTDED ' %4:
Rone 9.: 1 S e e I e 9 I i
-. M
e FINAL REPORT INDEPENDENT REVIEW 0F THE INSPECTION OF SHOREHAM NUCLEAR POWER STATION UNIT I i REACTOR PRESSURE VESSEL Prepared For LONG ISLAND LIGHTING COMPANY Shoreham Nuclear Power Station Wading River, New York . ' January 23, 1982 a By REINHART & ASSOCIATES, INC. Specialists in Nondestructive Evaluation P. O. Box 9802, Suite 173 Austin, Texas 78766 Prepared By: Eugene R. Reinhart President Date: March 8,1982 d
- . - - - - -~~
; -~ -
G,
- SUN 4ARY
,f fp>g T '
During the time period from December,1981 through February,1982, REINHART
& ASSOCIATES, INC., performed an independent review of the inspection his-
- tory of the Shoreham Nuclear Power Station Unit I Reactor Pressure Vessel (RPV), and also observed portions of the pre-service inspection of the same RPV at the powerplant site. This effort was performed at the request of the Long Island Lighting Company (LILCO), in accordance with LILC0 Purchase Ord-er No. 363108-1. The purpose of this inspection and review was to determine the adequacy of past and present-inspection efforts in complying with require-ments of the American Society of Mechanical Engineers (ASME) Codes and the Nuclear Regulatory Commission. Due to the compressed time schedule, this effort was conducted to verify the adequacy of key points in the inspection process only and not to review and/or witness every detail of the present inspection process, nor every past inspection record. When questions were raised from this cursory review, then the specific item in question was pur-sued in detail to a successful conclusion.
The results of the review indicated that the Shoreham reactor pressure ves-sel was inspected in accordance with the applicable ASME fabrication codes. The ASME Pre-Service Inspection also appeared to satisfy the requirements of applicable codes. The quality assurance programs of LILCO, Combustion Engineering (the RPV fab-ricator) and Nuclear Energy Services (pre-service inspection contractor) were reviewed and found to comply with the intent of applicable NRC requirements.
t o . LIST OF FIGURES Figure - Page 1 - Schematic of Typical Reactor Pressure Vessel (RPV) 2 - Shoreham Unit 1 RPV Weld Layout 3 - Shoreham RPV Weld Identification , 4 - NES Drawing of Vessel Weld Layout and Track Locations, showing Witness Areas 1 and 2' 5 - Photograph ~ of the Inspection of '<! eld 1 - 308C at Elevation
'618 in., by NES Inspectors, using the Longitudinal Wave Ultrasonic Examination Technique, as Witnessed by E. Reinhart on 12/10/81 (R&A Photograph) 6 -
Ultrasonic Longitudinal Wave (UT L-Wave) Examination of Base Metal next to Nozzle N30 (right side) Nozzle-to-Shell Weld at 2:54 P.M. on 12/10/81 (R&A Photograph) 7 - UT L-Wave Examination of Base Metal on Left Side of Nozzle N3D at 3:30 P.M. on 12/10/81 (R&A Photograph) 8 - View of Nozzle N3D Near RPV to Nozzle Weld, showing Smooth Paint-Free Surface Condition prepared for UT Examination (Area above N3D Identification Number shown on Nozzle) - 9 - View of Manual Longitudinal Ultrasonic Examination of RPV Weld and Base Metal at s 618" Elevation, as Witnessed by E. Reinhart on 12/10/81
~
10 - View of Ultrasonic Instrument Screen showing Peaked Signal from Reflector in RPV (mid-screen) 11 - View from Top of Shield Wall (Elevation s 618") of Pole Tracks used to Guide Automated Remote-Controlled Inspection System (R&A Photograph, 12/10/81) 12 - Schematic Drawing of Location of Tracks on RPV and Operation of the Remote-Controlled Inspection System 13 - View of RPV Calibration Block and Module containing Ultrasonic Search Units used with the Automated Inspection System i.55
C 14 - View of both RPV Calibration Blocks used for Calibration of Ultrasonic Inspection Instruments, Manual and Automated Ex-aminations (R&A Photograph on 12/03/81) 15 - NES Data Acquisition System as Witnessed by E. Reinhart on 12/03/81 16 - Closed-Circuit Video Screen Presentation of UT Data and Posi-tion of Search Units on RPV (Digital Numbers) 12/03/81 17 - Identification Card used for Closed Circuit TV Data Recorder 18 - View of Data Display and Acquisition System (12/03/81) 19 - View of System used to operate the Remote-Controlled ' Inspection System 20 - Inspection System (" sled") removed from Track prior to Scan at Weld I-308J Witnessed by E. Reinhart on 12/09/81 21 - RPV Nozzel NSB at N 415", near Witness Area 2 22 - View down from Witness Area 2 upon Sled during Remote Examination of Weld I-308J 12/09/81 e 0 0 (V .
DtteF:T- - Fort. YLGvihW
~
3 FINAL REPORT
/ lt*lt L INDEPENDENT REVIEW 0F THE INSPECTION OF
, SHOREHAM NUCLEAR POWER STATION UNIT I REACTOR PRESSURE VESSEL PROJECT LIL-1181 JANUARY 23, 1982
- P.O. 861793 Prepared For LONG ISLA'D N LIGHTING COMPANY Wading River, New York '
i l By REINHART & ASSOCIATES, INC. Austin, Texas l G
, , , , , m_ . - , . -
INTRODUCTION - During the time period from December, 1981 through January, 1982, REINHART & ASSOCIATES, INC. (R&A) performed an independent review of the inspection his-tory of the Shoreham Nuclear Powerplant Reactor Pressure Vessel (RPV), and also observed portions of the on-site pre-service inspection of the same RPV. This effort was performed at the request of the Long Island Lighting Company (LILCO), in accordance with LILC0 Purch.ase Order No. 363108, Rev. O, dated 11/30/81 and Rev.1, dated 12/28/81 (listed as References 1 and 2, and contained in Appendix A). . The purpose of this inspection and review was to determine the adequacy of the past and present inspection effort in compliance with the fabrication and pre-service inspection requirements of the American Society of Mechanical Engineers (ASME) Codes. Applicable ASME Codes are:
- 1. Construction:
- a. ASME Section III,1971 Edition, Summer,1972. Addenda -
, Rules for Construction of Nuclear Power Plant Components
,. (Reference 3).
- b. ASME Section V, 1971 Edition, Summer, 1972. Addenda -
Nondestructive Examination (Reference 4). l 2. Pre-Service Inspection: l l a. ASME Section XI, 1971 Edition, Summer, 1972. Addenda - Rules for In-Service Insp'ection of Nuclear Reactor Cool-
- ant Systems (Reference 5).
The Nuclear Regulatory Commission (NRC) Document 10CFR50, Appendix B - Quality Assurance Criteria for Nuclear Power Plants (Reference 6) also applies to the quality-control of this RPV inspection. Initially, the effort outlined by LILC0 was to include a day-to-day witness of the pre-service inspection by alternating members of an R&A inspection team for the duration of the inspection. Extensive document review was also requested. The team was comprised of two R&A Staff Members and one R&A Subcontractor, l l l
\
Each member of the team complied with the training, experience and educatior.al requirements of the American Society of Nondestructive Testing (ASNT) Document SNT-TC-1A,1975, for Level III Inspectors in the Nondestructive Examination (NDE) Method of Ultrasonic Testing (Reference 7). The team members selected by LILC0 were: John P. Porter and E. R. Reinhart of REINHART & ASSOCIATES, INC. and Richard I. Seals, a consultant to R&A. After conducting a two-week site review, LILCO changed the scope of work to eliminate the remaining site review and directed R&A to complete the effort of document and record review by mid-January,1982. This effort was expanded slightly by the addition of a review of radiographic inspection records to the scope of work. This review was conducted at the facilities of Combustion En-gineering (CE) in Chattanooga, Tennessee. The final effort, therefore, conduct-ed by RSA covered in this report, included the following:
- 1. Review of inspection plans, quality-assurance documents and inspection data (conducted at Shoreham Plant site and at the offices of R&A, Austin,. Texas).
- 2. Witness of pre-service inspection conducted at Shoreham Plant site.
- 3. Meetings conducted to discuss and resolve questions.
- 4. Review of radiographic film records of the inspection of the Shoreham RPV (conducted at the offices of Combustion Engineer-ing, Chattanooga, Tennessee).
The above effort was conducted in sufficient detail to verify the adequacy of selected key points in the inspection process, but did not review and/or wit . ness every step or detail of the present inspection process, nor every past inspection record. When questions were raised within a specific area, this area was pursued in detail until the questions were resolved. The specific areas selected for review were independently determined by R&A. The results of this effort are presented in the following sections: DOCUMENTATION REVIEW
. The documentation review was conducted to verify the adequacy and authenticity of the inspection records and also to determine that the inspection process had been controlled in such a manner that would produce a credible inspection at the required inspection sensitivity. There are two basic documents that are used to control the inspection of nuclear components:
- 1. Inspection Procedure - the inspection procedure is developed from the requirements of the applicable code and defines the 2_
= . _ - . . __
necessary steps that must be followed in order to perform an inspection. The procedure also details the training and qualification requirements for inspectors, and perform-
. ance requirements for the inspection equipment that must be used. The procedure also details the acceptance and rejec-tion criteria that will be used to evaluate any material discontinuities found during the inspection.
- 2. Quality Assurance Plan - in order to insure the credibility of an inspection, the NRC requires that fabricators, inspec-tors and operator-owners of nuclear powerplants follow a written plan, by which the inspection process is an indepen-dent function that reports directly to high levels of respon-sible management, and is also a process that can be audited.
These written plans are referred to as Quality Assurance (QA) Documents, Plans and/or Procedures. Since both of the above documents control the performance and credibility of an inspection, R&A first reviewed the inspection procedure for technical com-pliance with code requirements, then reviewed the applicable QA document for NRC compliance. The areas covered in reviewing the inspection documentation of the Shoreham RPV covered the following sequence:
- 1. Vessel Fabrication:
- a. Inspection Procedures
- b. QA Plan
- c. Inspection Records
- 2. Pre-Servi,ce Inspection:
- a. Inspection Procedures
- b. QA Plan Documentation review in each of the above areas is covered in the following sections:
FABRICATION From the review of the information in References 8 through 25, the following sequence of inspections were followed during fabrication of the RPV:
- 1. Shop RT - a shop radiographic inspection was performed in ac-cordance with ASME Section III (Reference 3) at the facilities of Combustion Engineering (CE) in Chattanooga, Tennessee. The applicable QA documents associated with the fabrication and in-spection are References 13 through 19. The procedure used for s
this inspection is listed as References 8 through 19. The radiographic inspection records are kept at the offices of CE and,a portion of these records were reviewed by members, E. R. Reinhart and C. C. Allen (see resume,R&A s, Appen- staff dix B), during the time period of January 5-6, 1982. The details of this review are covered in Appendix C. - All the inspection records, procedures and QA documents appeared to comply with the applicable code and regulatory requirements for fabrication of an RPV of this vintage.
- 2. Shop UT - after fabrication of the RPV, an Ultrasonic Examina-tion of the RPV welds was performed for the purpose of obtain-ing additional inspection information. This was not a code requirement at that time (sec. %-es I and 1)
The results of this inspection disclosed reportable ultrasonic indications in two of the no zle-to-vessel welds that led to a decision to repair these nozzles. The nozzles were repaired and re-inspected with RT and UT (Reference 16). From the results of this examination, one of the nozzles was accepted. The other nozzle-to-shell weld was still found to contain reportable indications and wase repaired for the second time. The nozzle-to-shell weld was then re-inspected and found to be acceptable. The reports, procedures and data covering the inspection and repair of these nozzles are listed as References to eroe ti (see.f;pr-e 3), From a cursory review of the material in References 20 and 21, and a site ex-amination of the radiographic examination records at Combustion Engineering (Appendix C), the inspection records for these two nozzle-to-shell repair welds appear to be in order and follow the applicable code requirements. PRE-SERVICE INSPECTION g . The Pre-Service Inspection (PSI) of the Shoreham vessel must isfy the re-quirements of the applicable ASME Code (Section XI, Reference (4)) and NRC docu-ments (10CFR50, Reference 6). The Pre-Service Inspection was conducted in two steps: 1) manual examination outside containment, and 2) manual and automated examination inside containment. The details of these inspections are covered in the following sections:
- 1. Manual PSI Baseline Outside Containment - the initial PSI of the Shoreham RPV was conducted after shipment of the RPV to the Shoreham site, but before the vessel was placed into con-tainment.
4
th.Y 1 This inspection consistpd of / manual Ultrasonic Examina-tion of the RPV m.a m. +n n m in weldsgu ea
.am-u- 'hwinninn 4mm e r ne,.
enn+cM
- nr en ~ im/
'SeI5s, sincE beEEUUh S:ci2d wouId be inaccessabledr$nce the vessel was placed into containment. The procedures and records covering this examination are listed in References 23, 24 and 25.
of +h.a sLs mmdo.n, . From a brief review of these recordy it appears that the inspection was con-ducted in accordance with the applicable codes and regulatory requirements.
- 2. Manual PSI Baseline Inside Containment - this inspection was essentially a repeat of the inspection conducted outside con-tainment on those vessel welds that may not be 'accessable to remote Ultrasonic Examination, once the vessel becomes opera-tional. The documents that apply to the PSI, including re-cords of the calibration standard reviewed by R&A, are list-ed as References 26 through 28. In addition .to RPV welds, an ultrasonic baseline of the RPV nozzle inner radius was also conducted. This technique uses an ultrasonic search unit, placed on the outside surface of the vessel wall, to scan the nozzle inner radius for service-caused cracks. This was not a specific code requirement, but may be useful for future in-service examinationss. .
cy nx m;n gf se n d <.e IOt *1 N M y'" A This procedure f as not reviewed, since this examination was beyond the scope of this effort. All of the documents reviewed appeared to comply with the applicable code and regulatory requirements. Site witness of manual Ultra-sonic Examinations is covered in a later section of this report.
^'JTC""T:0 ";I CASCLINE
- +G k spect %
.T W Automated PSI Baseline Inspectio was conducted ing a remote-controlled ultrasonic scanning system that inspected the RPV welds from the outside sur-face. The documents listed as References 29 through 33 apply to this inspec-tion and were briefly reviewed by R&A. ' These documents indicated that the critical steps, needed to qualify the function of the automated inspection equipment prior to its use on the pressure vessel, were anticipated. These documents were extensive and appeared to cover every major mechanical func-tion of the automated device. In addition to these basic documents, R&A re-quested that LILC0 supply test results verifying that the performance checks called out in the NES procedures were, in fact, performed. These test re-ports were supplied by NES to LILC0 and were reviewed by R&A. The test re-ports are listed as References 34, 35 and 36, respectively. These reports verified that the inspection system had performed the required scanning func-tion under simulated inspection conditions. T - '
5
SITE WITNESS The second major phase of this project was the witnessing of pre-service in-spection activities at the Shoreham Powerplant. This effort was conducted in order to insure that the various steps detailed in the inspection proce-dures were, in fact, being followed, and included review of inspector certi-fication documents, instrument calibration checks and other site-related documents. This effort was conducted during the time period from December 1 through December 12, 1981. The results were reported to the LILC0 site re-presentative, Mr. Eugene Nicholas, on both a daily and weekly basis (Refer-ences 37 through 39). Manual and automated inspections were randbmly select-ed and witnessed. The results are discussed in the following sections: Manual Ultrasonic Inspection - The witness effort in this area included a check of the ultrasonic instrument calibration activity to verify that it was being performed in accordance with the NES procedure. One particular weld examination was followed from calibration to hands-on examination, to re-calibration. This examination was the longitudinal (0 ) wave ultrasonic ex-amination of weld 1-308C, and surrounding base material. The weld, and the point at which the inspection process was monitored, is shown in Figure 4 as Witness Area 1. This weld was selected since the initial shop examination disclosed acceptable indications in this weld (Reference 14, Paragraph 3). Figures 5 through 10 depict various stages of the actual inspection. These photographs were taken by R&A Staff Member E. Reinhart, after approval by LILC0. The NES inspectors appeared competent and were very willing to discuss the details and results of their inspection. This was only one check out of the many inspections being conducted; however, this, team did appear to be follow-ing the NES procedure exactly. It is interesting to note that reportable, but acceptable, indications were again found in this area of the RPV, indi-cating r c & n of correlation between the pre-service field examination l and the original shop inspection. Automated Ultrasonic Inspection - The witness activity in this area included:
- 1. Examination of pole tracks mounted near RPV wall (Figures 11 and 12).
- 2. Discussion of system operation with NES inspectors.
l 3. Witness of calibration of remote inspection system (Figures 13 and i 14). l l 4. Witness of NES data display and acquisition system, and witness of control system during automated inspection scan (Figures 15 through 19).
- 5. Witness of remote inspection from Witness Area 2 during actual scan of weld (Figures 20, 21 and 22).
l i s 6 l _ . _ _ _ . _ _ _ _ _ _ - - - - ~ ~ - -
From the witness activity and meetings at the site, the following comments are made regarding the automated system:
- 1. The automated system used in this examination uses tracks mount-ed on poles (" pole-tracks"), with the poles secured to the in-side of the round shield wall, in close proximity to, but not touching, the wall of the RPV. The " pole-tracks" provide a guide track for an inspection device (sled) to move up and down the length of the RPV. A rotating arm on the sled allows scans to be performed at right-angles to the direction of the vertical
" pole-tracks". Thus, scans can be accomplished in both the hori-l zontal and vertical directions. With this capability, since the poles are positioned at several areas around the RPV, a consider-able volume of the RPV can be reached for inspection.
- 2. The inspection arm contains a module with three ultrasonic search units; two shear-wave (both 45 ) and one longitudinal wave.
These techniques are called for in the Code.
- 3. The control system has a means to monitor the spatial position of the inspection device on the RPV wall, controls the scan speed and extends and/or rotates the various components to ac-complish either horizontal or vertical scans of the RPV welds and adjacent base material.
- 4. The data display and acquisition system uses three standard ultrasonic instruments. Permanent recording of information
, .is accomplished using a strip-chart recorder and closed-circuit
' television system.
- 5. This type of system has been extensively used world-wide over the past eight years by at least two in-service inspection con-
, tractors, and does not represent new or untried technology (Ref-erence 40).
- 6. The overall automated system appears to satisfy the code and .
regulatory requirements that are relevant to this RPV. CONCLUSIONS From the information reviewed in this effort, the shop and pre-service inspec-tions of the RPV appear to conform to the applicable ASME Code and NRC re-quirements for the Shoreham No. I reactor pressure vessel. f
s . I i i REFERENCES
- 1. LILC0 Purchase Order No. 363108 and Scope of Work No. Q101, Rev. O, dtd 11/30/81 (in Appendix A). '
i
- 2. LILC0 Purchase Order No. 363108-1 and Scope of Work No. Q101, Rev. 1, dtd 12/28/81 (in Appendix A).
- 3. ASME Section III, 1971 Edition, Summer 1972 Addenda - Rules for Construction of Nuclear Power Plant Components. *
- 4. ASME Section V,1971 Edition, Suamer,1972 Addenda - Nondestructive Examina-tion.
- 5. ASME Section XI, 1971 Edition, Summer, 1972 Addenda - Rules for In-Service Inspection of Nuclear Reactor Coolant Systems.
'6. Nuclear Regulatory Commission (NRC) Document 10CFR50, Appendix B - Quality Assurance Criteria for Nuclear Power Plants.
- 7. ASNT, Recommended Practice, No. SNT-TC-1A (1975 Edition).
- 8. Combustion Engineering, Inc., M&P Spec. No.: 2.4.1.3(c), Process Specifica-tion for Radiographic Examination of Commercial Nuclear Components, August 22, 1969.
- 9. Above, with Addendum 1(a), October 30, 1970.
- 10. Above, with Addendum 2(a), January 6,1971.'
- 11. Above with Addendum 3(a), October 20, 1971.
- 12. Above with Addendum 4(a), December 5, 1972.
- 13. Stone & Webster (S&W) Engineering Co'poration, r Inspection Report, Shop Quality Control, Trip Report No.1, J.0. No.11600.50,10/7-9/69.
- 14. Report No. 7, 2/2-4/72.
- 15. Report No. 8,8/16-17/73.
- 16. Report No. 13, 10/21-23/73.
- 17. Report No. 14, 11/4-9/73.
- 18. Report No. 15, 11/13-15/73.
9
- 19. Report No. 19, 2/22-27/79.
- 20. Joint Report to LILC0 by the Shoreham Unit #1 Evaluation Team; General Electric, Combustion Engineer.ing, Southwest Research Institute, Stone Webster, " Report of the Shop Ultrasonic Examination of the Shoreham Nu-clear Power Station Unit I Reactor Pressure Vessel Welds", April 27, 1973. .
de twered to
- 21. LILCO Report, Final Report on Reactor Vessel Repair (it: 1 identi"
? LILC 0
"~
le Kne 'r' 0LIL- ,c$93 tf, 5~ P.UcVArro m 1f; p. Abyflg.,,,.919' f t' & S $d N w A ude t-f ro //
- 22. NES Report No. 81A0447, " Manual Ultrasonic Examination of the Shoreham Nuclear Power Station One Reactor Pressure Vessel", Rev.1, April 18, 1977.
- 23. Wlock, Eugene C. , LILC0 letter to Mr. J. Kohlmeyer, CE, " Reactor Pres-sure Vessel Weld Identification, Shoreham Nuclear Power Station - Unit 1, TM-4-551, October 4, 1974.
- 24. US NRC Office of Inspection and Enforcement, Inspection Report No. 50-322/75-08, 7/9/75. .
Sci,on.en F.x. Wcmeru nda m N G
" Manual Ultrasonic Examination of the Shoreham Reactor 25.APressure erecke, T.F.,l Vesse by Nuclear Services, Inc., Shoreham Nuclear Power Sta-tion, W.0. 4430, May 24, 1976.
- 26. NES Document 80A0482, "Shoreham Nuclear Power Station Unit I, Pre-Service Inspection Program Plan", Prepared for LILC0 by NES, Rev. G, 2/16/81.
- 27. NES Document 80A0462, " Manual Ultrasonic Examination Procedures for Re-actor Pressure Vessel, Circumferential and longitudinal Welds, Long Is-land Lighting Company, Shoreham No. 1", June 10, 1975.
- 28. General Electric Letter to LILCO, Shoreham Nuclear Power Station Unit #1, UT Calibration Standards.
- 29. NES Document 80A0470, " Automated Ultrasonic Examination Procedures for Reactor Vessel Nozzle Welds", Rev. No. 1, 11/3/78.
- 30. NES Document 80A0480, " Automated Ultrasonic Examination Procedures for Reactor Vessel Welds", Rev. No. 2, 10/12/81.
- 31. Shoreham Nuclear Power System - 1 Final Safety Analysis Report, pp.121-26 through 121-26c, Revision 19, September, 1980, and Exhibits 121 25-1 (describes the scanner).
- 32. NES Document No. 80A4340, Functional Test Procedure, BWR Vessel Scanner (80D063), Rev. O, 3/23/81.
9
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4
- 33. NES Document No. 85A149, Procedure for the Certification of Surface-Oriented Ultrasonic Examination Heads, Rev. 0, 9/9/81.
- 34. NES Document 80A4340, Results of Tests 1 through 10, 3/27/81.
- 35. NES Document 80A3720, Shoreham Vessel Scanner, On-Site Fit-Up Procedure, Rev. O, 3/11/81.
- 36. NES Document No. 80A4438, Report on Shoreham Vessel Scanner On-Site Fit-Up Procedure, Rev. O, 4/30/81.
- 37. Reinhart, E. R., Daily Activity Reports to E. Nicholas, LILCO, as follows:
- a. 12/01/81
- b. 12/02/81 .
- c. 12/03/81
- d. 12/04/81
- e. 12/05/81
- 38. Reinhart, E. R., Weekly Progress Report No.1, Independent Review of RPV inspection Submitted to LILCO, 12/08/81.
- 39. Reinhart, E. R., Daily Activity Reports to E. Nicholas, LILCO, as follows:
- a. 12/07/81
- b. 12/08/81 ,
- c. 12/09/81
- d. 12/11/81
- 40. Southwest Research Institute Brochure, " Mechanized Inservice Examination Equipment", 1974, pp. 6 and 7.
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1 FIGURE 3 - Shoreham RPV Weld Identification showing Welds selected for RT Data Revieu.
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_ _. _ m m _ , , FIGURE 5 - Photograph of the Inspection of Weld 1-308C at Elevation 618 in. , by NES Inspectors, using the Longitudinal Wave Ultrasonic Examina-tion Technique, as witnessed by E. Reinhart on 12/10/82 (R&A Photo-graph). Smooth Paint-Free Metal Surface is shown in the Examination Area at Bottom Lef t of Photograph. IS
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FIGURE 6 - Ultrasonic LongitIdinal Wave Examination of Base tietal Next to N3D (right side) Nozzle-to-Shell Weld at 2:54 P.fi. on 12/10/81 (R&A Photograph). P ,* '" **
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. _ 3, q FIGURE 8 - View of Nozzle N3D near RPV to Nozzle Weld, showing Smooth, Paint-Free Surfacea Condition prepared for UT Examination (Area above N3D Identification Number shown on Nozzle).
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FIGURE 9 - View of Manual Longitudinal Ultrasonic Examination of RPV Weld and Base Metal at s 618" Elevation n witnessed by E. Reinhart on 12/10/81. The Shiny, Paint-Free Surface of the Area Ur. der-going Examination is shown at and to the Left of the Search Unit. l8
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Plant / Unit _ Date Tape # Time Welds Scans CalDataPkg* Sleds CH1 CH2 CH3 Sound Beam Angles Sled Orientation Examiner I.R Operator FIGURE 17 - Identification Card used for Closed Circuit TV Data Recorder.
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12/09/81. W _ ~. _ _ . . _
e - APPENDIX A t LONG ISLAND LIGHTING SCOPE OF WORK - Purchase Order No. 363108-1, Rev. O, 11/30/81 and Rev. 1, 12/28/81. e e C e [
A . APPENDIX B Resunds Calvin C. Allen, R&A John P. Porter, R&A Eugene R. Reinhart, R&A Richard I. Seals, Consultant to R&A i
C APPENDIX C REVIEW 0F RADIOGRAPHIC INSPECTION RECORDS AT COMBUSTI0ft ENGINEERING '
.CHATTAN0OGA, Til.
e l I ) t t... i l
A mur DOCUMENT NO. REV. NUCLEAR ENERGY SERVICES, INC. PAGE OF -- PRESERVICE INSPECTION OF THE SHOREHAM NUCLEAR POWER STATION-UNIT ONE REACTOR PRESSURE VESSEL Prepared Under Project 5536 for the Long Island Lighting Company By Nuclear Energy Services, Inc. Danbury, Connecticut 06810 Project Apolication Prepared By Date APPROVALS TITLE / DEPT. SIGN ATU R E DATE
" """"7"-
m's0-REVIS 0) .00 PAGE OF NUCLEAR ENERGY SERVICES. INC. r OATE "#[ g DESCRIPTION APPROVAL
DOCUMENT NO. A" y m _ U : l-NUCLEAR ENERGY SERVICES. INC. TABLE OF CONTENTS Page 1.0
SUMMARY
4 _2.0__ DI' SCUSSIONS - - _ _ _ - _ _ - - -
-- - - .4 ..
____ 2.1 General-_ _4- _ 2.2 Equipment 4 2.3 Techniques -- --- - - - - -
--- -- - -5 --- -
2.3.1 Ultrasonics ----- - - - - -- -- -
-5 2.3.2 Visual 5 3.0 EXAMINATION DETAILS AND RESULTS 6 3.1 Ultrasonic Examinations 6 3.1.1 Automated Examination 6 3.1.2 Manual Examinations 7 3.2 Visual Examinations 7 APPENDICES A. Examination Procedures B. Personnel Certifications C. Equipment Certifications D. Couplant Certifications E. Calibration Block Certifications F. Calibration Data Sheets and Exam Result Sheets m e -om
- -- e ew -4
, . e e -
- h e. e i h
- B DOCUMENT NO.
Fp M 5' PAGE OF d a N NUCLEAR ENERGY SERVICES. INC.
- 1.
SUMMARY
The following report covers preservice examinations of the SNPS-1 Reactor pressure vessel performed in December 1981. This information supplements NES Report No. 81A0447 which covers reactor pressure vessel examinations performed prior to this period. The specific examinations performed are listed in Table 1 (Ultrasonic) and Table 2 (Visual) of this report.
- 2. DISCUSSION 2.1 GENERAL The ultrasonic and visual examinations were performed in accordance with Nuclear Energy Services,Inc. (NES) procedures that were designed to meet the intent of the 1971 ASME boiler and Pressure Vessel Code, Section XI 1971 Edition through the Summer of 1972 Addenda and NES specification 80A0448, " Quality Assurance Program Plan - Inservice Inspection, Shoreham". Copies of the examination proce.dures are included as Appendix A. The test data, including calibration sheets and examination results, is included in Appendix F.
Examination personnel performing the 1981 baseline examinations were certified in accordance with established NES procedures and with SNT-TC-1 A, the American Society for Non-Destructive Testing document which deals with personnel certification. Copies of the personnel certifications of each individual performing the examinations are included as Appendix B. 2.2 EQUIPMENT Sonic Mark I and Krautkramer USL 32 UT instruments were used in the manual examinations. A three channel ultrasonic system employing Automation Industries 580 UT Instruments was used for automated examinations. The search units (transducers and wedges, where used) were of varying types manufactured by AI, KB Aerotech, and NES. The details of the ultrasonic instrument - search unit combination can be found on the ! calibration data sheets in Appendix F. Equipment certifications can be found in Appendix C. The couplant used in the manual exams was Ultagel 11 manufactured by Echo Labs; the automated exams required ' demineralized water supplied by LILCO, eythlene glycol manufactured by Dow chemical and Phot Flo manuf actured by Kodak. The couplant certifications are included in Appendix D. l Calibration blocks used to perform the examinations were supplied by GE and NES Certifications for the NES supplied blocks are in Appendix E. l l l l
, DOCUMENT NO.
a w -- NUCLEAR ENERGY SERVICES, INC. 2.3 TECHNIQUES 2.3.1 Ultrasonics All ultrasonic examinations of the vessel shell welds (longitudinal,
. circumferential, dome, meridional and nozzle to shell), were examined with 00 straight beam and 450 angle beam techniques; Inner Radius exams were examined with 450 and 700 techniques. The
.. _ vessel flange weld was examined with 00, 50, 10.50 and 450 techniques.
-The weld examinations covered the weld, heat affected zone and base metal as defined in the examination procedures.
The ultrasonic instrument - search unit combinations were calibrated before each examination on the appropriate calibration block. Periodic calibration checks were performed at the completion of each four hour period of examination and/or at the change of examination personnel, equipment etc., and at the completion of the examination of each similar series of welds as defined in the examination procedures. 2.3.2 Visual Visual examinations were performed as required on the RPV Close Head Nuts, Studs, Washers, Spare Bushings, Clad Patches, Dryer Hold Down Brackets, Guide Rod Brackets, Steam Dryer Support Lugs, , Feedwater Sparger Brackets, Upper Surveillance Specimen Baskets, Core Spray Lines, Feedwater Spargers, Shroud, Shroud Support Plate, Steam Seperator and Dryer, Vessel Cladding, CRD Housing to Vessel Welds, Core AP and Liquid Poison Piping, Welds on Shroud Support Assembly, and the In-Core Flux Monitor Housing to Vessel Weld.
.-em - - - = = . - m o== .
DOCUMENT NO. p m aw
; PAGE OF 6 = NUCLEAR ENERGY SERVICES, INC.
- 3. EXAMINATION RESULTS Required examination of all areas and items were completely performed except as noted in this Section. No reportable indications were detected during performance of this examination workscope. Areas which did not receive full examination coverage are listed in Paragraphs 3.1 and 3.2.
3.1 ULTRASONIC EXAMINATIONS
~
Limitations to required coverages areas note below. 3.1.1 Automated Examination
- 1. Circumferential Weld No. 4-308A.
Vessel stabilizings at azimuth 450, 1350, 2250 and 3150 and elevation 544.0" limited the coverage areas.
- 2. Circumferential Weld No. 4-308B A tapered condition due to plate mismatch precluded examination of two small patches of weld.
- 3. Circumferential Weld No.1-313 l
This weld joins plates of differing thickness with a machined taper of the thicker plate. Coverage of approximately 1" above
- the weld and 2" below the weld was limited due to the tapered l
intersection. l l 4. Longitudinal Weld No. T-308A Coverage was reduced by approximately 4" in the area of nozzle N13A.
- 5. Longitudinal Weld Nos.1-308E and 1308F Coverage of the uppermost portions of these welds was limited due to interference with vessel stabilizer lugs.
- 6. Longitudinal Weld Nos.1-308G,1-308H and 1-3083 The lower portions of these welds were not covered due to interference from the tapered area (see item 3 above).
1
- 7. Longitudinal Weld Nos.1-307A,1-307B and 1-307C The upper portion of those welds were not covered due to interference from the tapered area. (See item 3 above).
rresyto rst w o u m
DOCUMENT NO. s' e mur b'U' " NUCLEAR ENERGY SERVICES, INC. 3.1.2 Manaual Examinations
- 1. Longitudinal Weld No.1-308C A small scan area at the 696" elevation was obstructed by a thermocouple.
. 2. Circumferential Weld No. 3-318 (closure head)
Nozzle locations reduced coverage at 00 and 1800 azimuths.
- 3. Meridonal Weld Nos. 1-318B, 1-318D, 1-318F and 1-318H (closure head)
Closure head lif ting lugs obstructing portions of scan areas
- 4. Meridional Weld No.1-306D (bottom head)
Nozzle placement interfered with scan area.
- 5. Feedwater nozzles N4A and N4C Nozzles are obstructed by N12A and N12B respectively.
3.2 VISUAL EXAMINATIONS Limitation to required coverage areas are note below: .
- 1. Closure Head Studs Studs 1,26, 27,39,40 and 52 were completely inspected. The remaining studs were installed and inspected from the flange up to 41 3/4". An ASME Section III exam was performed by Reactor Controls, l Inc. on uninspected areas in lieu of an NES visual exam.
- 2. Closure Head Busings 325-05-01 through 52 An ASME Section III exam ns performed by Reactor Controls, Inc.
on the 52 installed bushings in lieu of an NES visual exam. RPV Interior Visual exams were performed on 100% of the accessible components required to be examined under category B-N-1 and B-N-2. FORM 8 NES 205 2/80
a= mm any DOCUMENT NO. U " '- PAGE OF NUCLEAR ENERGY SERVICES, INC. TABLE 1 A AREA OF EXAMINATION - VERTICAL WELDS (AUTOMATED EXAMINATIONS) 5-7/8" SHELL COURSE Exam Coverage (inches) Weld No. % From To 1-308A 300 553 618 1-308B 1500 553 618 1-308C 2700 553 618 1-308D 00 104 703 1-308E 1200 403 553 1-308F 2400 403 553 1-308G 300 253 403 1-308H 1500 253 403 1-3083 2700 253 403 6-7/8" SHELL COURSE Exam Coverage (inches) Weld No. % From To 1-307A 18o 104 140 j 1 227 253 1-307B 1380 104 253 1-307C 2580 104 253
DOCUMENT NO. cc a 6' " PAGE OF NUCLEAR ENERGY SERVICES, INC. TABLE 1 A AREA :OF EXAMINATION - CIRCUMFERENTIAL WELDS (AUTOMATED EXAMINATIONS) 5-7/8" SHELL COURSE Exam Coverage DEG Weld No. % From To 4-308A 553" 340.030 26.650 4-308A 553" 106.410 115.370 4-308A 553" 245.400 278.020 4-308B 403" 359.950 355.530 4-308B 403" 106.410 124.240 4-308B 403" 147.810 165.640 4-30SB 403" 236.530 254.360 4-308B 403" 266.100 283.930 5-7/8" 7/8" SHELL COURSE Exam Coverage DEG Weld No. Q From To
- ,w 1-313 253" 17.700 35.520 1-313 253" 2;.I10 165.640 1-313 253 21,3.400 283.930
_KoJmt
- MH2200 2/@o - - - . - . . . _ . _ . _ .. . . _ _ _ _ _ _ _ - -- -
muy DOCUMENT NO. J9 mm PAGE OF
" d -'"
NUCLEAR ENERGY SERVICES. INC. TABLEIB RPV SHELL/ CLOSURE HEAD / FLANGE LIGAMENTS WELDS (Manual Exams) Weld No. Description 6-307 Shell Weld @ 104" elevation 4-306 Bottom Head Weld ' 5-30'6 Bottom Head Weld 2-318 Closure Head Flange Weld 3-318 Closure Head Weld 1-308A (el 618" - 703") Shell Weld @ 300 Azimuth 1-308B (el 618" - 703") Shell Weld @ 1500 Azimuth 1-308C (el 618" - 703") Shell Weld @ 2700 Aximuth 1-318A-H Closure Head Meridional Welds 1-306A-H Bottom Head Meridional Welds 2-306A-F Bottom Head Meridional Welds 325-01-01 through 52 Closure Head Studs 325-02--I through 52 Closure Head Nuts 325-01-01-L through 52-1 Closure Head Nuts 325-01-01-L through 52-L RPV Flange Ligaments 4-324A through D Stabilizer Brackets (
DOCUMENT NO, e mm my PAGE OF NUCLEAR ENERGY SERVICES, INC. TABLEIB RPV NOZZLE WELDS (Manual Exams) Weld No. Description 4-317 Head to Vent Nozzle (N7) Weld 4-317-r Vent Nozzle (N7) Inner Radius 2-317A Heas to Instrument Nozzle (N6A) Weld at 00 Azimuth 2-317A-r Head to Instrument Nozzle (N6A) Inner Radius 2-317B Head to Instrument Nozzle (N6B) Weld at 1800 Azimuth 2-317B-r Instrument Nozzle (N6B) Inner Radius 15-316A RPV to MS Nozzle (N3A) Weld at 720 Azimuth 15-316 A-r MS Nozzle (N3A) Inner Radius 15-316B RPV to MS Nozzle (N3B) Weld at 1080 Azimuth 15-316B-r MS Nozzle (N3B) Inner Radius 15-316C RPV to MS Nozzle (N3C) Weld at 2520 Azimuth 15-316C-r MS Nozzle (N3C) Inner Radius 15-316D RPV to MS Nozzle (N3D) Weld at 2880 Azimuth 15-316D-r MS Nozzle (N3D) Inner Radius 4-316 A RPV to FW Nozzle (N4A) Weld at 450 Azimuth 4-316 A-r FW Nozzle (N4A) Inner Radius 4-316B RPV to FW Nozzle (N4B) Weld at 1350 Azimuth 4-316B-r FW Nozzle (N4B) Inner Radius 4-316C RPV to FW Nozzle (N4C) Weld at 2250 Azimuth 4-316C-r FW Nozzle (N4C) Inner Radius 4-316D RPV to FW Nozzle (N4D) Weld at 3150 Azimuth 4-316D-r FW Nozzle N4D Inner Radius 19-314 A RPV to 3P1 Nozzle (N8A) Weld at 1050 Azimuth 19-314 A-r JPl Nozzle (N8A) Inner Radius 19-314B RPV to JPl Nozzle (NSB) at 2500 Azimuth 19-314B-r JPl Nozzle (NSB) Inner Radius ll-316 A RPV CS Nozzle Weld at 900 Azimuth Il-316 A-r CS Nozzle (NSA) Inner Radius ll-316B RPV to CS Nozzle (N5B) Weld at 2700 Azimuth Il-316B-r CS Nozzle (N5B) Inner Radius 15-315 RPV to CRD Return Nozzle (N9) Weld at 1460 Azimuth 15-315-r CRD Return Nozzle (N9) Inner Radius 13-314 A RPV to Inlet Nozzle (N2A) Weld at 300 Azimuth 13-314 A-r Inlet Nozzle (N2A) Inner Radius 13-314B RPV to Inlet Nozzle (N28) Weld at 60 0 Azimuth 13-314B-r Inlet Nozzle (N2B) Inner Radius 13-314C RPV to Inlet Nozzle (N2C) Weld a 900 Azimuth 13-314C-r Inlet Nozzle (N2C) Inner Radius
DOCUMENT NO. N ~ d e E%_any d ' PAGE OF NUCt. EAR ENERGY SERVICES. INC. TABLE IB (Continued) . RPV NOZZLE WELDS (Manual Exams) l Weld No. Description 13-314D RPV to Inlet Nozzle (N2D) Weld at 1200 Azimuth 13-314D-r Inlet Nozzle (N2D) Inner Radius 13-314E RPV to Inlet Nozzle (N2E) Weld at 1500 Azimuth 13-314E-r RPV Inlet Nozzle (N2E) Inner Radius 13-314F RPV to Inlet Nozzle (N2F) Weld at 2100 Azimuth 13-314F-r Inlet Nozzle (N2F) Inner Radius 13-314G RPV to Inlet Nozzle (N2G Weld at 2400 Azimuth 13-314G-r Inlet Nozzle (N2G) Inner Radius 13-314H RPV to Inlet Nozzle (N2H) Weld at 2700 Azimuth 13-314H-r Inlet Nozzle (N2H) Inner Radius 13-3143 RPV to Inlet Nozzle (N23) Weld at 3000 Azimuth 13-3143-r Inlet Nozzle (N23) Inner Radius 13-314K RPV to Inlet (N2K) Weld at 3300 Aximuth 13-314K-r Inlet Nozzle (N2K) Inner Radius 5-314 A RPV to Outlet Nozzle (NI A) Weld at 00 Azimuth 5-314 A-r Outlet Nozzle (NI A) Inner Radius 5-314B RPV to Outlet Nozzle (NIB) Weld at 1800 Azimuth 5-314B-r Outlet Nozzle (NIB) Inner Radius 1 I l
DOCUMENT NO. ' im am mur PAGE OF L 6 '" NUCLEAR ENERGY SERVICES, INC. TABLE 2 VISUAL EXAMS Weld No. Description 325-01-01 through 52 Closure Head Studs 325-02-01 through 52 Closure Head Nuts 325-03-01 through 52 Closure Head Washers 325-05-51 through 56 Closure Head Buslings RPV-01-P Vessel Clad Patch at 900 Aximuth RPV-02-P Vessel Clad Patch at 2700 Azimuth RPV-03-P Vessel Clad Patch at 450 Aximuth RPV-04-P Vessel Clad Patch at 1350 Aximuth RPV-05-P Vessel Clad Patch at 2250 Aximuth R PV-06-P Vessel Clad Patch at 3150 Aximuth RPV-01-i A-D Dryer Hold Down Brackets RPV-02-1 A & B Guide Rod Brackets RPV-03-1 A-D Steam Dryer Support Lugs RPV-04-i A-H Feedwater Sparger Brackets RPV-05-i A-H Core Spray Brackets RPV-06-i A-H Upper Surveillance Specimen Brackets R PV-07-i Lower Surveillance Specimen Brackets RPV-08-i Core Spray Lines RPV-09-i Feedwater Spargers R PV-10-i Jet Pumps RPV-l l-i Shroud RPV-12-1 Shroud Support Plate RPV-13-i Core Plate Hold Down Bolts R PV-14-1 Steam Separator and Dryer R PV-14-i Vessel Cladding (Representative) RPV-16-i CRD Housing to Vessel Welds R PV-17-i Shroud Support Lugs R PV-I S-i Core A P and Liquid Poison Piping R PV-19-i Welds on Shroud Support Assembly R PV-20-1 Underside of Core Plate RPV-21-1 In-Core Flux Monitor Housihng to Vessel Weld e-wuvmunum ,
4 4 In the Matter of .
' kJ.,-,I2 lb *.
LONG ISLAND LIGHTING COMPANY (Shoreham Nuclear Power Station, Unit 1) Docket No. 50-322 (OL) r CERTIFICATE OF SERVICE I hereby certify that copies of LILCO'S AMENDED RESPONSE TO SUFFOLK COUNTY'S REQUEST FOR PRODUCTION OF DOCUMENTS and LILCO'S FURTHER RESPONSE TO SUFFOLK COUNTY INTERROGATORIES were served upon the following people by first-class mail, postage prepaid, on April 9, 1982, except for those with an asterisk who were served by Federal Express or by hand on April 9, 1982. Lawrence Brenner, Esq.* Atomic Safety and Licensing Administrative Judge Appeal Board Panel Atomic Safety and Licensing U.S. Nuclear Regulatory Board Panel Commission U.S. Nuclear Regulatory Washington, D.C. 20555 Commission Washington, D.C. 20555 Atomic Safety and Licensing Board Panel Dr. Peter A. Morris
- U.S. Nuclear Regulatory Administrative Judge Commission Atomic Safety and Licensing Washington, D.C. 20555 Board Panel U.S. Nuclear Regulatory Bernard M. Bordenick, Esq.
Commission David A. Repka, Esq. Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Dr. James H. Carpenter
- Washington, D.C. 26555 Administrative Judge Atomic Safety and Licensing David J. Gilmartin, Esq.
Board Panel Attn: Patricia A. Dempsey, Esq. U.S. Nuclear Regulatory County Attorney Commission Suffolk County Department of Law Washington, D.C. 20555 Veterans Memorial Highway Hauppauge, New York 11787 Secretary of the Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555
l 4 Herbert H. Brown, Esq.* Howard L. Blau, Esq. Lawrence Coe Lanpher, Esq. 217 Newbridge Road Karla J. Letsche, Esq. Hicksville, New York 11801 Kirkpatrick, Lockhart, Hill, Christopher & Phillips Matthew J. Kelly, Esq. 8th Floor Staff Counsel, New York 1900 M Street, N.W. State Public Service Commission Washington, D.C. 20036 3 Rockefeller Plaza Albany, New York 12223 Mr. Mark W. Goldsmith Energy Research Group Mr. Jay Dunkleberger 400-1 Totten Pond Road New York State Energy Office Waltham, Massachusetts 02154 Agency Building 2 Empire State Plaza MHB Technical Associates Albany, New York 12223 1723 Hamilton Avenue Suite K San Jose, California 95125 Stephen B. Latham, Esq.* Twomey, Latham & Shea 33 West Second Street P. O. Box 398 Riverhead, New York 11901 Ralph Shapiro, Esq. Cammer and Shapiro, P.C. 9 East 40th Street New York, New York 10016 D O. T,c % Daniel O. Planagaq' Hunton & Williams 707 East Main Street P. O. Box 1535 Richmond, Virginia 23212 DATED: April 9, 1982 __}}