ML20082Q553
| ML20082Q553 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 12/06/1983 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 7726N, NUDOCS 8312120247 | |
| Download: ML20082Q553 (34) | |
Text
__
[ Commonwealth Edison
/
^
one F.rst Nations! Plaza. Chicago, Ithnois C
(j} Address Reply to. Post Office Box 767 Chicago. Illinois 60690 December 6, 1983 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Generating Station Units 1 and 2 Braidwood-Generating Station Units 1 and 2 Environmental Qualification of Equipment NRC Docket Nos. 50-454, 50-455, 50-456, and 50-457 References (a):
July 70, 1983, letterProperty "Letter" (as page type) with input value ""July 70, 1983" contains a sequence that could not be interpreted against an available match matrix for date components." contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. from B. J.
Youngblood to D. L.
Farrar.
(b):
May 20, 1983 letter from B. J. Youngblood to D. L. Ferrar.
Dear Mr. Denton:
This is to provide additional information regarding the environmental qualification of safety-related equipment at Byron and Braidwood stations.
Reference (a) provided an SER on this topic and requested additional information on specific technical issues which were identified as incomplete at the July 1983 site audit at Byron.
Attachment A to this letter contains Commonwealth Edison's response on all issues except mechanical equipment qualification and justification for interim operation of electrical equipment.
Those responses will be provided by the end of this month.
In reference (b) the NRC requested a list of safety-related mechanical equipment located in harsh environment areas and summary information on that equipment.
The requested information is being compiled and will be submitted by December 19, 1983.
We understand that the NRC expects to re /lew detailed qualification information on three items from this list to confirm the adequacy of our qualification program.
At present, it appears that environmental qualification testing of six items of electrical equipment will not be completed prior to the target fuel load date.
Accordingly, our justifications for interim operation of the plant with incomplete qualification of these six items will be provided for NRC review.
The justification for NSSS Limitorque valve operators will be submitted by December 15, 1983.
Similar justifi-cations for Barton switches, Crosby relief valve position indication switches, Rockwell hydrogen recombiners, Borg Warner main steam atmospheric relief valves, Model 85440, and Borg Warner damper actuators will be provided by December 30, 1983.
The qualification testing of some r312120247 831206 PDR ADOCK 05000454 0
A I
pg
H. R. Denton December 6, 1983 or all-of these items may act ually be completed prior to fuel load of Byron 1, but these six justirications are being developed as a contingency.
Please direct further questions regarding this matter to this One signed original and fifteen copies of this letter and the attachment are provided for NRC review.
Very truly yours,
}hr 5" T.R. Tramm
. Nuclear Licensing Administrator 1m Attachment A
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ATTACHMENT A ADDITIONAL INFORMATION REGARDING ENVIRONMENTAL QUALIFICATI0b 0F SAFETY-RELIEF EQUIPMENT FOR BYRON AND-BRAIDWOOD STATIONS f:
NOTE:
The information presented here addresses specific sections of the NRC's SER provided in the July 20, 1983_ letter from B.
J.
l
.Youngblood to D. L. Farrar.
The SER excerpts are identified by.section number.
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3.11.3.1 Completeness of Eauipment Important to Safety In order to demonstrate compliance with 10 CFR 50.49, the following information is required to be submitted by the applicant prior to granting of an operating license:
(a) a list of all non-safety-related electrical equipment located in a harsh environment whose failure under the postulated environmental conditions could prevent the satisfactory accomplishment of safety functions by the safety-related equipment.
A description of the methods used to identify this equipment must also be included.
The non-safety-related equipment identified must be included in the environmental qualification program.
(b) a list of additional safety-related electrical equipment which is required to function to mitigate design basis events other than LOCAs or HRLBs and which is located in the harsh environment created by the design basis event.
(c) a list of all post-accident monitoring equipment currently installed or that will be installed prior to plant operation that is specified as Category 1 and 2 in Regulatory Guide 1.97 Rev. 2 and is located in a harsh environment.
The equipment identified must be included in the environmental qualification program.
Response
(a)
Equipment, valve and instrument indexes were searched to identify safety related equipment.
Schematics, piping and instrument details and wiring diagrams were then reviewed to determine safety related functions.
The Byron /Braidwood electrical design does not utilize any non-safety-related electrical equipment whose failure under the postulated environmental conditions could prevent a satisfactory accomplishment of safety functions by the safety-related equipment.
All Byron /Braidwood electrical circuits / equipment are designated either Class lE or Non-Class lE.
Associated cables are not utilized on Byron /Braidwood design.
Class lE components of an ESF division are physically and electrically separated from Class lE components of the redundant ESF division as well as Non-Class lE components that could cause loss of redundancy as the result of a design basis event affecting failure of these components.
The physical and electrical separation is in accordance with the guidelines presented in IEEE 384-1974 and Regulatory Guide 1.75 (with certain exceptions as documented in Appendix A to the FSAR).
The separation requirements are incorporated in the design through the project Electrical Separation Design Criteria and project procedures.
For cases where the circuit design requires an interface between Class lE and Non-Class lE circuits, specific analyses are performed on a case by case basis to show that any postulated failures in the Non-Class 1E circuit will not prevent a Class 1E circujt from performing its safety function.
These analyses are documented and maintained on file along with other design documents.
t
. (b)
As stated in the introduction to the Byron /Braidwood Equipment Environmental Qualification Report, the equipment which is identified in the report and included in the Byron /Braidwood Environmental Qualification Program is all electrical equipment required for emergency reactor shutdown, containment isolation, reactor core cooling, containment heat removal, core residual heat removal or prevention of significant release of radioactive material to the environment.
The list of equipment included in the program includes not only Class lE equiment which is required to mitigate a LOCA or HELB, but it also includes all other equipment designated as Class lE.
Qualification for all Class lE equipment located in a harsh environment created by any design basis event will be completed prior to fuel load or a justification for interim operation w311 be prepared and submitted in accordance with 10 CFR 50.49.
(c)
See Table A for listing of Post Accident Monitoring instruments.
This equipment is included in the environmental qualilfication program.
Included in this Table is equipment required by the TMI Action Plan (NUREG-0737).
This equipment will be qualified prior to fuel-load.
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3.11.3.3.5 Aging The aging program requirements for Byron electrical equipment are defined in Section 4, Category I of NUREG-0588.
The degrading influences of temperature, radiation, vibration, and electrical and mechanical stresses should be considered and included in the aging program.
Any justifications for excluding pre-aging of equipment in type testing should be established based on equipment design and application, or on state-o f-the-art aging techniques.
A qualified life is to be established for each equipment item.
In addition to the above, a maintenance / surveillance program should be implemented to identify and prevent significant age-related degradation of electrical and mechanical equipment.
The applicant has committed to follow the recommendations in Regulatory Guide 1.33, Revision 2, " Quality Assurance Program Requirements (Operation)," which endorses American National Standard ANS-3.2/ ANSI N18.1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants," in the FSAR.
This standard defines the scope and content of a maintanence/ surveillance program for safety-related equipment.
Provisions for preventing 02 detecting age-related degradation in safety-grade equipment are specified and include a) utilizing experience with similar equipment, b) revising and updating the program as experience is gained with the equipment during the life of the plant, c) reviewing and evaluating malfunctioning equipment and obtaining adequate replacement components, and d) establishing surveillance tests and inspections based on reliability analyses, frequency and type of service, or age of the items, as appropriate.
The applicant has described generally a program based on the above but has not adequately addressed use of operating experience and surveillance as they relate to equipment qualification.
This area will remain open until an adequate program description is provided.
In addition, the staff will review the implementation of the program at a later date.
Response
See Attachment A Documentation of Structured History File, Retrieval and Sort Menu and Flexible Retrieval Examples.
This is a detailed explanation of a segment or the Ceco structured maintenance history file which addresses the mechanism Byron and Braidwood Stations propose to for allowing operating experience, based on equiment performance,
- use, to flag age related degradation.
Through this mechanism, the appropriate measures of increased or decreased preventive maintenance activities, or design corrrections, in accordance with other established programs, can be accomplished.
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3.11.3.4 Outstanding Equipment For safety-related items not having complete qualification documentation, the applicant has provided commitments for corrective action and schedules for completion.
For items not expected to have full qualification, analyses must be performed in accordance with paragraph (1) of 10CFR50.49 to ensure that the plant can be operated safely pending completion of environmental qualification.
These analyses must be submitted to staff prior to granting of an operating license.
Section 3.11.3.1 discusses additional equipment which may require qualification based on 10CFR50.49.
These items must be identified to the staff and included in the qualification program.
Response
Justifications for interim operations will be provided for six items in December, 1983.
The applicant has made a number of commitments to replace or retest unqualified equipment prior to fuel load, as described in Section 4.2 of the environmental qualification program submittal.
Prior to issuance of an operating license, the applicant must confirm that all equipment replacement and testing commitments have been fulfilled or must justify interim operation with equipment not fully qualified.
A program has been implemented at Byron Nuclear Station to verify that the equipment presently installed at the station is the same as that for which qualification has been established.
A designated equipment qualification field engineer has been assigned the responsibility to verify that the installed model is the correct (qualified) model or to initiate the required actions to change out the equipment with the applicable qualified mode.
All unqualified equipment will be replaced prior to fuel load.
Presently over ninety percent of the unqualified 9quipment has been replaced.
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3.11.4.1.2 Equipment Requiring Additional Information and/or Corrective Action Appendix B identifies equipment in this category.
Corrective action or deficiencies are noted by a letter relating to the legend identified below.
Response
Responses to open items are listed in the same sequence as identified in Appendix 8.
In some instances, Appendix B inaccurately listed the status of components requiring corrective actions.
Some of those discrepancies are corrected here.
Valve Operator, Limitorque. SMB Series 1)
For harsh Non-NSSS Limitorque Valve Operators Environmental Qualification is completed and contained in Binder CQD-009948.
2)
Limitorque Valve Operators on NSSS that may be exposed to HELB/LOCA Environments will be replaced during the first refueling outage.
Justification for their interim operction will be provided December 15, 1983.
Hydraulic Valve Operator, Borg Warner, Model No. 38971 Environmental Qualification is complete and contained in Binder CQD-009487 Hydraulic Valve Operator (MS Atmospheric Relief Valves), Model No. 85440, Borg Warner Test results will become available in February, 1984.
Justification for interim operation will be provided by December 30, 1983.
Hydraulic Valve Operator, Borg Warner Model No. 85460.
Environmental Qualification is in progress.
The report will be available from Borg Warner after January 1984.
Affected are valve actuators for Containment Purge Valve Actuators 1,2 VQ001A, 2A and 1,2VQ001B, 2B.
The safety function of these valves and actijators is to remain closed during all phases of plant operation.
The valves are opened by their respective cctuators during planned reactor shutdowns to purge the containment of cirborne particulates so as to allow safe personnel access within three hours.
Until the vendor environmental qualification report is received and Ovaulated the respective power supplies will remain disconnected by station procedure.
Once the valves are closed and the electric power supply disconnected, the valves will remain closed and will not open due to any environmental event.
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3.11.4.1.2 Response (Cont)
Junction Box,-Borg Warner This item was qualified as part of Hydraulic Valve Operator, Model No.
38971.
Evaluation is contained in Binder CQD-009487.
Junction Box, Westinghouse,-Model No.-W/L 23686 This equipment consists of a 2 section power range excore neutron detector, type WL-23686 detailcd on Westinghouse drawing E-2231 Rev. 13.
Environmental Qualification testing was completed by Westinghouse.
Equipment Qualification Data Package EQDP-ESE-8 Rev. O is presently under evaluation.
Test results appear good and the ev'aluation will be completed prior to fuel load.
HVAC Control Panel, Johnson Controls Initial Environmental Qualification testing was completed and evaluated.
A number of outstanding items are presently being reevaluated or retested.
Evaluation of seismic qualification of device mountings will be completed by Nov. 30, 1983.
Some devices are in retest for additional radiation exposure, sea listing below.
Retesting and reevaluations are scheduled to be completed prior to fuel load.
Based on the initial evaluation that accounted for over 97% of ccmponents no new problems are expected to arise from this additional testing.
'Cumponents undergoing additional radiation aging:
General Electric Terminal Blocks General Electric Switchboard Wire Gould ITE Fuse Pullout Pyrotronics Smoke Detector United Electric Pressure Switch Wallace and Tierman Chlorine Detector Weed RTD OT-2 Switch EZC-Light Love Flow Controller, 548187-8115-8174 Moore Industries Differential Pressure Relay
. United Electric Temperature Switch Radiation Detector, General Atomics, RD-12 The environmental qualification is completed and is evaluated in Binder CQD-007951.
Flow Indicating Switch, Barton, 288A The final test report is due December 31, 1983.
The evaluation will be completed prior to. fuel load.
Justification for interim operation will be provided by December 30, 1983.
=
Response
Sandia test reports ADND 80-2149 RV1and "A Study of Strong Synergism in Polymer Degradation".have been reviewed along with other industry reports on cable failures.
There is no evidence that Byron cables will be susceptible to any significant age related degradation.
Failures in industry were induced by conditions not normal to Byron Station while the Sandia testing was conducted on cables of a material composition different from the Byron cable materials.
A specific maintenance / surveillance program for cables inside the containment will not be developed.
Existing maintenance and surveillance programs coupled to our Structured History computer program will identify root causes of problems, including cable related anomolles.
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3.11.'4.1.2 Response (Cont)
Hand Switch, Westinghouse, OT2 This is included in Johnson Controls test program listed previously.
Pressure Switch, United Electric, J-302-5164 This is included in Johnson Controls Test Program listed previously.
Level Transmitter, Barton, 764-763 These instruments were relocated above flood level.
Pressure Transmitter, Veritrak, 76PH2 Environmental Qualification testing is completed by Westinghouse and contained in Binder EQDP-ESElB.
Evaluation will be completed prior to fuel load.
RTD, RDF, 21204 Environmental Qualification and evaluation are completed and contained in Binder EQDP-ESE-6.
Pressure Transmitter, Barton - 351 Environmental Qualification and evaluation are completed and contained in Binder EQDP-ESE-21.
Flow Controller, Love, 54-8187-8115-8174 This is included in Johnson Controls test program listed previously.
Flow Transmitter, Hays, 252A Hays Flow T :ansmitters were replaced with Validyne P361D-FT508 units which are n)w located in mild environment areas.
Differential Pressure Relay, Moore Industries, ADM Position Light, Westinghoue, EZC Temperature Switch, United Electric, C303D-103 These three items are included in Johnson Controls test program listed previously.
Current Relay Signal Converter, Masonellan, 8005A Environmental Qualification completed, with evaluation to be completed t
prior to fuel load.
I Flow Transmitter, Rosemount, 11538 Environmental Qualification and evaluation completed and contained in Binder CQD-006044.
I
3.11.4.1.2 Response (Cont)
Limit Switch-(I/C), NAMCO, EA-180 Environmental Qualification and evaluation completed and contained in Binder CQD-010001.
Positioner, ITT, NH90, NH91 ITT NH91 and NH95 damper actuators are used at Byron Station.
Environmental Qualification is completed and formal test report is due Dec. 15, 1983.
Based on a preliminary review of the test data no outstanding items are expected and the evaluation should be completed prior to fuel load.-
Switchboard Wire, Rockbestos, Firewall SIS Evaluation is completed and contained in Binder CQD-01009.
Hydraulic Valve Operator, Anchor / Darling-Environmental Qualification and evaluation completed and contained in Binder'CQD-009941.
Terminal Block,-Marathon, 1600 Series Marathon NUC 1600 series terminal blocks were retested and found acceptable for power and control circuitry.
Instrument circuits in LOCA/HELB areas were removed from terminal blocks and spliced.
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i, 3.11.4.1.3 Equipment Considered Acceptable or Conditionally-Acceptable Based on the staff review, the items identified in Appendix C have been determined to be acceptable, pending implementation of the maintenance / surveillance program.
Response
The General Surveillance System a computer program for initiating maintenance and surveillance activities, has been loaded into the station computer.
In addition to other functions, this program will track all activites on Environmentally Qualified equipment.
Information is presently being loaded into this program which will allow it to initiate E.Q. related maintenance and surveillances.
7726N
3.11.4.2 Environmental Qualification Audit The staff and EG&G Idaho personnel conducted an audit of the Byron plant qualification flies and installed equipment on June 21-23, 1983.
The following observations and conclusions were made as a result of the audit:
Issue:
Not all essential equipment potentially exposed to flooding has been identified.
For example, it was observed during the plant walkdown that the juction box for a valve motor operator required to operate post-LOCA was located beley the flood level in containment but had therefore conduct a plant walkdown to identify all equipment and interfaces (junction boxes, splices, etc.) which are below the postulated flood levels and either relocate these items or demonstrate qualifcation for submergence.
The applicant must confirm that this work has been completed prior to fuel loading.
Response
A walkdown was performed to determine all essential equipment that was located below the potential flood level.
Through a formal program, all ossential equipment has been relocated above flood level.
Issue:
In several of the equipment reviews, it was determined that insufficient attention had been given to the acceptance criteria for qualification tests and their applicability to plant specific requirements (see discussions of Marathon terminal blocks and Conax penetrations below).
The acceptance criteria for all equipment in the program should therefore be reviewed.
The applicant should notify the staff when this review is completed and describe any changes in qualification status of equipment. The staff will select several items of equipment for additional review to verify that this area has been acceptably resolved.
Response
In order to make the environmental qualification data more retrievable for engineering review, and more effective for station maintenance, all qualification flies for equipment located in harsh environment have been reformatted.
Twenty-two of the twenty-eight non-NSSS environmental qualification binders have been re-reviewed and reformatted at this time.
During the review, particular attention was given to assure that the acceptance criterin for the qualification tests enveloped the acceptance criteria required by the equipments plant specific application.
Based on retest and reevaluation of the environmental qualification of Marathon terminal blocks it was determined that terminal blocks would not be used for safety'related instrumentation circuits within the containment since the acceptance criteria for the qualification test did not envelope Byron's requirements for instrument circuits.
Qualification status did not change for any additional equipment.
In many cases the reevaluation of data allowed for increased qualified life by calculating the qualified life based on specific plant locations rather than a worst case environment.
Issue:
A number of discrepancio. existed between the qualification summary sheets supplied with the environmental qualification submittal and the information in the plant files, most of which were satisfacto-rily addressed during the audit.
The summary sheets were furnished to the staff on June.17, 1982 and did not reflect the most recent qualification data.
Revised and updated sheets should be made available to the staff for review.
Response
Revision of data sheets is taking considerably longer than anticipated.
Information being incorporated into the data sheets already exists in the Environmental Qualification Equipment Binders.
During the recent three months data la the binders was reevaluated and reformatted before being made available for entry into the data sheets.
Data sheets reside inside two separate computer files where data entry is limited to the use of only one terminal per file.
Revision of data sheets is optimistically scheduled for completion and transmittal by December 31, 1983.
Any specific information required before this data can be obtained from existing equipment binders.
Issue:
In our review of individual items of equipment during the audit, several questions could not be satisfactorily resolved.
These are listed below and must be addressed by the applicant prior to licensing.
Anchor / Darling Main Steam Isolation Valve - the audit team was unable to resolve questions concerning the correct values for postulated pressure and temperature during DBA, the required operability time, and the time period after an accident during which failure may not occur.
In addition, the failure modes and effects analysis and identification of valve accessories should be clarified.
This file should be revised and rearranged to address these concerns and be made available for further review by the staff.
Response
Additional vendor test data was obtained to resolve the above concerns.
New data, along with existing data was reevaluated and reformatted.
Resulting infomation is contained in Binder CQD - 009941 which will be transmitted to E.G. and G.
Idaho on November 22, 1983, for review.
Issue:
Marathon 1600 Series terminal blocks - the staff reviewed this item for instrumentation applications.
The. acceptance criteria
=specified included only the ability to withstand an applied 7
- voltage.and current and to not exceed a specified level of
. leakage current during exposure to LOCA conditions.
Insulation
. resistanca values were specified in the-design specification but were not measured during LOCA exposure.
In addition, the. leakage l
current: tests results indicated that insulation resD'tance, although not directly measured, was probably less than the value required for instrumentation circuits.
The applicantistated that
- the test results can apply to control circuits only and has committed to retesting.or replacement of terminal blocks in this application as a result of the review.
. Response This' concern is resolved in response to Marathon NUC 1600 terminal blocks in part 3.11.4.1.2.
I Issue:. Conax electrical penetrations - the qualification file did not i
contain results of insulation resistance measurements during exposure to LOCA conditions, as required by IEEE 317-1976.
The checklist in the file did not. address this omission and accepted the existing incomplete test data as sufficient.
The applicant
- contacted the vendor during the audit and determined that.these data.are.available'and demonstrate the acceptability of the instrumentation penetrations for this application.
Tnis.
information will be incorporated into the' plant environmental qualification file.-
i
Response
Additional information has been obtained from CONAX and incorporated in the respective equipment binders CQD-009952, 009824, 009498 and 009944.
Issue:
The applicant also committed to providing information on
. surveillanceLto be used to. monitor the condition of the
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p penetrations during the life of the plant.
Response
4 Af ter completion of Appendix J testing, CONAX penetrations surveillance 0111 be performed in accordance with Section 3/4.6.1.2 of the technical i
specifications for mechanical integrity of the penetrations.
Electrical integrity of penetations are verified through periodic
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' instrument loop calibration /surveillances or periodic performance testing of equipment in accordance with technical specification requirements.
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Failure of' penetrations to meet these periodic surveillance requirements results in appropriate corrective actions utilizing the CECO maintenance repair programs.
This results in the ability to track the condition of plant equipment over the life of the plant as discussed in answer to question 3.11.3.3.5.
Issue:
Rosemount 11538 transmitter - the applicant should confirm that the transmitter will be replaced at proper intervals.
Response
Equipment Qualification Binder CQD - 006044 has been tansmitted to Byron Station.
Maintenance / surveillance data is being entered into the General Surveillance computer program described in section 3.11.4.1.3.
Qualified life is incorporated in the Maintenance and Surveillance Schedule of the equipment binder.
Transmitters in zone A-8 are qualified for 21 years.
Tag numbers are:
1FT-AF011 through AF018 1FT-CS011 through CS016 2FT-CS0ll through CS016 Transmitters in zone A-10 are qualified for 7 2/3 years.
Tag numbers are:
2FT-AF011 through AF018 Issue:
Reliance fan motor for RCFC - the comparison of postulated chemical spray conditions versus tested conditions should be furnished to the staff for review.
Response
See Attachment B which is duplicated from Section F-1 of Binder CQD-009644.
Test conditions exceeded postulated chemical spray conditions by over 200%.
Issue:
Okonite and Dekorad cables - the applicant committed to provide information on surveillance techniques to be utilized for cables inside containment.
SYSTEM MANUAL Page 44 Date: 09/13/82 DOCUMENTATION OF STRUCTURED HISTORY FILE RETRIEVAL AND SORT MENU 1A.
E.I.D.#
18.
Unit IC.
System 10.
Equipment Number lE.
Equipment Type l
['S flJ' h+ 5) 2.
Location 5
3.
Function #
V yf 4.
NPROS Vendor Code Mg 5.
Manufacturer's Name gly g u
6.
Model #
7.
Drawing #
J 8.
Class 9.
Size 10.
Maximum Occurrances (Auto. Flag) 11.
Date of Completion (2 Dates) 13.
Priority of W.R.
14.
Department 15.
Outage 16.
Actual Hours 17.
Foremans Code 18.
Contractor Name 19.
Serial #
20.
P or C Indicator 21.
Tool I.D.#
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22.
EQ 23.
S.T.I.
24 Maintenance Code 25.
Maintenance Cause 26.
S.I.#
27.
Manufacturer's Name of Part Attachment A
kIb SYSTEM MANU5 L Page 45 i
Date: 09/13/82 i
00CUMENTATION OF STRUCTURED HISTORY FILE FLEXIBLE RETRIEVAL EXAMPLES (Numbers under Examples refer to item numbers on Retrieval and sort Menu -- Page 45)
- 1. List all history on #2 Reactor Feed Pump on Unit #1.
- 1A
- 2. List all history between January 1, 1981 and December 31, 1981 for the Mechanical Maintenance Department on the make-up demineralizer system.
- 1C
- 12
- 14
- 3. What history is on work request #12345?
- 11 4
List all rotating element failures on Ingersoll Rand pumps, between January 1, 1981 and January 1, 1902.
- 5
- 12
- 24
- 5. How many times have I used stores item #222333 in a class lE environment between January 1, 1982 and July 1, 1982?
- 8
- 12
- 26
- 6. List all history that contractor Smith Company worked on within the last year.
- 12
- 18 7.
List all history on manufacturer Pacific Pump model
- 87654112.
- 5
- 6
- 8. List all history performed by the Electrical Maintenance Department on 3-inch motor operated valves on the heater drainage system between January 1, 1981 and December 31, 1981.
- 1C' #1E
- 9
- 12
- 14 Attachment A
SYSTEM MANUAL Page A6 Date: 09/13/82 DOCUMENTATION OF STRUCTURED HISTORY FILE FLEXIBLE RETRIEVAL EXAMPLES (Cont'd)
- 9. How many times have I used Asco solenoids on safety-related equipment between January 1, 1982 and July 1, 1982?
- 8
- 12
- 27
- 10. What location and position is Target Rock relief valve, serial #198 in?
- 19
- 11. List all history on Unit #1 Outage between February 1, 1982 and March 1, 1982.
- 15
- 12
- 12. List all jobs that tool #12345 was used on between January 1, 1982 and July 1, 1982.
- 12
- 21 INFORMATION ONLY Attachment A
~
/
SYSTEM MANUAL Page 55 Date: 03/04/83 00CUMENTATION OF STRUCTURED HISTORY FILE MAXIMUM OCCURRENCE / FREQUENCY ADDENDUM Maximum Occurrence / Floating Frecuency Examoles Initial conditions Max. Occur.
=
3 Freq.
=
6 months Maintain following parameters (initially set to 0)
Counter
=
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Action Date (Date of current corrective
=
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action)
Pointer Date (Set to date of first
=
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corrective action and then updated as required to maintain window period (freq.)).
Counter will be updated each time a corrective action is entered for an EID#,
Any addi.tional action will be triggered by counter reaching max. occur, value.
Once reaching max.
occur. value, counter will be reset as shown in examples.
If conditions are changed by the user, last action date becomes the pointer date, and the counter is set to one.
Use the following corrective action dates to step through the examples:
1 - 1/05/83 2 -'2/10/83 Y
h']hi[gp7% pg 3 - 7/06/83 Yf,g[g A - 7/25/83 l
03 5 - 9/30/83 Initial conditions:
Max. Occur.
3
=
Freq.
6 months
=
Counter
=
0 Action Date
=
(( [ ~ [-
Pointer Date
=
Attachment A
SYSTEM MANUAL Page 56 Date: 03/04/83 DOCUMENTATION OF STRUCTURED HISTORY FILE MAXIMUM OCCURRENCE / FREQUENCY A00ENDUM Maximum Occurrence / Floating Frequency Examoles.(Cont'd) 1 - 1/5/83 Corrective action after entry Counter 1
=
Action Date 01 05 83
=
Pointer Date 6I O5 83
=
Compare counter to max. occur.
Counter not equal to max. occur.
No action required 2 - 2/10/83 Corrective action after entry Counter
=
2 Action Date
=
02 10 83 Pointer Data UT UT TT
=
Compare counter to max. occur.
Counter not equal to max. cccur.
No action required 3 - 7/06/83 Corrective action after entry Counter
=
3 Action Date
=
07 06 83 Pointer Date 6 T. 6 5 83
=
Counter equals max. occur.
Compare action date to pointer date for frequency of 6 months.
Period is greater than 6 months - no printout.
Update pointer date to next corrective action.
Pointer date = 2/10/83.
Decrement counter from 3 to 2.
After action Counter 2
=
Action Date
=
07 06 83 gg TU gT f,
p Q$pg g,g pu jg 9pl;
%l y9p Pointer Date g
=
m-i utdeY Attachment A
SYSTEM MANUAL Page 57 Date: 03/04/83 1
DOCUMENTATION OF STRUCTURED HISTORY FILE MAXIMUM OCCURRENCE / FREQUENCY ADDENDUM Maximum Occurrence /Floatino Frecuency Examples (Cont'd) 4 - 7/25/83 Corrective action after entry Counter 3
=
Action Date
=
07 25 83 6Y TF IT Pointer Date
=
Counter equals max. occur.
Compare action date to pointer date for frequency of 6 months.
Period is less than 6 months; print message to Maint. Dept. flagging EIDf; (hard copy report generated).
Update pointer date to last corrective action.
Pointer date = 7/25/83.
Decrement counter from 3 to 1.
After action
~
Counter 1
=
Action Date
=
6 Y Y_ 5 I I Pointer Date
=
5 - 9/30/83 Corrective action after entry Counter
=
2 Action Date 09 30 83
=
Pointer Date 6Y YI I3
=
Compare counter to max. occur.
Counter not equal to max. occur.
No action required.
INFORMATION' ONLY Attachment A
SYSTEM MANUAL Page 58 Date: 03/04/83 DOCUMENTATION OF STRUCTURED HISTORY FILE MAXIMUM OCCURRENCE / FREQUENCY ADDENDUM Maximum Occurrence /Floatino Frecuency Examoles (Cont'd) 6 - The users will have the capability of increasing or decreasing the maximum occurrence field or floating frequency at any time.
If they do so, the last action date becomes the pointer date and the action date is blank until the next corrective action, and the counter is set at one.
On 1/20/84 the user changes conditions.
Change conditions to:
Max. Occur.
=
5 12 months Freq.
=
1 Counter
=
Action Date
=
Pointer Date =
[ _9 3_ 0_ _ 8_ 3_
G e
INFORMAIl0N ONLY l
l l
l t
Attachment A
w 3'A m m, 1 'k % m 4
^tt" "" "*
mm SARGENT&LUNDY NM,c-ch' QCpC R, o,,,
Safety-Related Non-Safety-Related Page \\
of A C"C^
Cl O_m M %)M 6h Prepared by b.
0 8 \\ d 52%M Date
\\A-Project b(UVi f biMdDCd, _
Rev'ewed by Date o
~
Prol. Nok
\\1 N6NEquip.N o\\CY_.h Approved by Data i
i h
k.
ON
\\
Lh
%~ ha k
% w wnw%g %w W Atw ucom % 6 6ddmco,,
l ~tes 't eMEE\\ %
~~
1p w
\\
m2.o h we&o m ia wsodS@
e as u 6
.pqc -
a a.--
p e4:
ww -
p g.
- -+
e
+a-+<.-
-ee
.em-- - - - -
1
-r e
ma gw-
..-p-I_
... _. __ _ _ L. q. _
j i
r j
g
=..w-
_,,,y
='==-r-e e-.-hm
4 I'. Attachment B 1 I g f
Comparison of pressure:
(-
. The peak pressure of 50 psig is enveloped through the testing at 50 psig during the initial transients.
. The transient pressure of 20 psig is enveloped during the first 21 hour2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> exposure to 83 psig.
. The steady state pressure of 5 psig for one year is not explicitly enveloped.
There is no known way to simulate accelerated effects of pressure.
However, the maximum requirement of 50 psig for three hours at the peak temperature was simulated.
The bl.ocks were then
~
exposed to 83 psig which exceeds the maximum requirement by 66%,
for a duration of 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> which exceeds the maximum duration (3h) by 1300%.
At these tested extremes, no failures were attributed to pressure.
Based on this, it is concluded that the 5 psig require-ment would not be a failure mechanism.
1 Comparison of chemical spray:
Two areas must be examined when evaluating chemical spray.
They are the ph level and the spray saturation.
During testing, the ph was maintained within the range of 8.5 to 10.5.
The minimum requirement for Marble Hill is 8.5 (ref. section 6.5.2 of FSAR).
Thus it is concluded that the Marble Hill requirements were
(
met.
The spray saturation is defined as the gallons per square foot seen within the containment during the accident.
The spray saturation is determined from the following:
(spray gpm/f t ) X (Duration
)
Spray
=
2
(
Saturation (gal /ft )
(density
)
(in minutes)
The spray saturation from testing 1s determined from the following, i
l tabulated test data:
Spray Dengity Duration in Spray
[
,in gpm/ft minutes saturation (gal /ft )
0.04 180' 7.2 0.04 180 7.2 0.15 2520 378 i
0.50 180 90 l.5 40,320 60,480
=.. - -
Spray saturation during. testing = 60,962.4
(
,'Ns> The spray saturation for Marble Hill is determined through references-to the FSAR.
The Marble Hill spray system consists of two trains A& B.
Train A consists of 219 nozzles while train B is designed r
. Attachment B
'e with with 253 nozzles for a total of 472 nozzles (ref. FSAR 6.5.2.2).
(
The spray system is designed to deliver 15 gpm to each nozzle (ref.
FSAR 6.5.2.2).
Thus the spray system is designed to deliver a total of 7080 gpm.
The containment radius is 70 ft. (ref. FSAR figure 3.8.1).
Thus we can calculate the Marble Hill spray density as follows:
Spray 7080 gpm 7080 gpm
= 0.46 gpm/ft y (70)~
Density cont. srea If we assume the spray to remain functional for 30 days, the Marble Hill spray saturation becomes 2
19,872 galfft (0.46 gpm/ft )
(43200 min)
=
The test conditions exceed the Marble Hill requirements by over 200%.
h.
We thus conclude that the Marble Hill spray conditions were enveloped.
4 c.
hP e
G
(
/
Attach. ment B dnWJew,v/ 7'o C c4 x --6s t' compncueo" of w'ce ca*'wsl'nnaciaJ be6 v
)
yS try [>
- rnsqR & c P eet.i<
TL'm P ' S 2 G *t* **k resre o cauan reviu : agooi= e vsj
?. pg a,9sra su erma-ve.w 83 */a rrid RdiAJ Ti M e.
rwo pea.ks Jia-si pear ( o <c. asc~r= b a.+ cs ci P ec h &~
r D c). are m c., pg. ic x,cor) aso maacie. hat smused ramp pac f e 214
'Tesreci coio am on : az o v es6 aoo *e= e 4 h aso i= e h/h
~~-
rew es. reme..rwt=, a p % em w u ou n s.e ine eate
>+u.c. esrcado, sritre reme t iso 3: e uers i;i:
TetiTek eTed3 sr e t Emf'.' 250 P Q /* /6 f.' 2' 6??f <Witi6:tG
~
rc.w
/43,as edi/J 7, ne.
' 'f*Re5E rn tra rst e b / / Ar4< pecess; rofsg e A.
(
Towr-d pez < p< e s s ;
e pg,,s,g g 44 gg sj,,,,n,u,n,, pc,am 3
3 3 % m e r;&iiv c10 Tim e.
r run26Le holl twou3tead,7 mess,* pt)psa (2. 21 h.
TeSTGc) Pc c.SS :
7o -sig g 76 f
2 b'? S* 2 C.'b M6 pr ess. 90pugj /Ca */o irrilitC,tA). PreE*8-STondg eiere pt-esS. s;=vy e' up to Ig.
TcsYcc) 43r-esS.
s'ds -tyg ( tar 270 A /6 y').-U ?s 'f{h'f
/4 ".d, m/f ?6/JJ 7wi2 chern cnl.
rnise&'.e HsL L =~ c.96 s em/Fr* Jo e epy />. (uuria-5 E~ ' h p
i-c a c k nd).
f.c s T c o N ch (t c N *,, iSca i;'m /PT -je r-7c/ (rv). t@. IS'>.'-Gos) r L
tunetc hJl acracaraiu= (e.qs &Pycg)[2yA)[6cn.% )
r.
d&2 9'S/,72
~tc5T coon,was:(r66 vm/rr)[74)(2t)(as) = l5% 6"#' '
tr>ee6.va-n ak
<M I,4A a 6~
~
1/6
, ' Table A#
R.G. 1.97, Itev. 3 & NUREG-0737 PAM INSTRUMENTS Nato: This is a listing of those local mounted instruments which are currently specified for Post Accident Monitoring service and are being or have been procurred to the equipment qualification requirements of a Catedory 1 or 2 component (per R.G. 1.97, Rev. 3) Unit 1 instruments are listed only. The primary element (transmitter, sensor, etc.) is listed with the implication that the balance of the instrument loop, required to support display and recording functions, is to be qulified a.'.co.
However, the environment is mild since the balance of each instru-ment loop is located in the Aux. Electric & Main Control Rooms.
R.G. 1.97 NUREG-0737 Instr.
Instr.
Instrument No.
Service Cat.
Act. Item COL-ROW EL.
Loc. Dwg.
Location IPT-403 RCS WR Pressure 1
N/A G-1
- Cont. 377 M821-3 1PL75J IPT-405 RCS WR Pressure 1
N/A L-5 Cont. ~377 M821-3 IPL66J ITE-413A RC Temperature WR THot 1
N/A D-7 Cont. 390 6/20E-1-3521 LM 1TE-423A RC Temperature WR T ot 1
N/A H-7 Cont. 390 6/20E-1-3522 LM H
1TE-433A RC Temperature WR T ot 1
N/A H-6 Cont. 390 6/20E-1-3527 LM H
1TE-443A RC Temperature WR THot 1
N/A D-5 Cont. 390 6/20E-1-3524 LM
.lTE-413B RC Temperature WR TCold 1
N/A D-8 Cont. 390 6/20E-1-3521 LM 1TE-423B RC Thmperature WR T old 1.
N/A H-9 Cont. 390 6/20E-1-3522 LM C
ITE-433B RC Temperature WR T old 1
N/A H-4 Cont. 390 6/20E-1-3527 LM C
1TE-443B RC Temperature WR TCold 1
N/A D-4 Cont. 390 6/20E-1-3524 LM 1LT-501 SG WR Level 1
N/A A-8 Cont. 377 M321-1 1PL50J ILT-502 SG WR Level 1
N/A L-7 Cont. 377 M821-2 IPL67J 1LT-503 SG WR Level 1
N/A G-1 Cont. 377 M821-3 IPL75J 1LT-504 SG WR Level l'
N/h D-1 Cont. 377 M821-4 1PL52J ILT-517 SG NR Level 1
N/A A-6
- Cont. 401 M822-4 IPL69J 1LT-518 SG NR Level 1
N/A C-10 Cont. 412 M823-1 LM 1LT-519 SG NR Level 1
N/A A-4 Cont. 412 M823-4 1PL57J lLT-527 SG NR Level 1
N/A G-1 Cont. 377 M821-3 1PL75J 1LI-528 SG NR Level 1
N/A J-10 Cont. 412 M823-2 LM I
l:
i 4
5 l
d h
Table A R.G. 1.97. Rev. 3 & NUREC-0737 2/6
~
l'AM INSTRUMENTS R.G. 1.97 NUREG-0737 Instr.
Instr.
Instrument No.
Service Cat.
Act. Item COL-ROW EL.
Loc. Dwg.
Loca tiJ.t ILT-529 SG NR Level 1
1:/A G-11 Cont. 412 M823-2 1PL71J 1LT-537 SG NR Level 1
N/A G-1 Cont. 377 M821-3 1PL75J lLT-538 SG NR Level 1
N/A K-7 Cont. 412 M823-2 LM 1LT-539 SG NR Level 1
N/A G-ll Cont. 412 M823-2 1PL71J
.1LT-547 SG NR Level 1
N/A A-6 Cont. 401 M822-4 1PL69J 1LT-548 SG NR Level 1
N/A A-8 Cont. 412
'M823-1 LM' 1LT-549 SG NR Level 1
N/A A-4 Cont. 412 M823-4 1PL57J ILT-459 Pressurizer Level -
1 N/A.
A-8 Cont. 377 M821-1 1PL50J
.1LT-460 Pressurizer Level 1
N/A F-10 Cont. 377 M821-1 LM
. ~.
1LT-461 Pressurizer Level 1
N/A D-1 Cont. 377 M821-4 1PL52J 1PT-934 Containment NR Pressure 1
N/A C-1 Cont. 426 M824-4 LM V-12 Aux.
426 M831-ll
.1PT-935 Containment NR Pressure 1
N/A B-2 Cont. 451 M825-4 LM S.7-12 Aux.
451 M825-4 1PT-936 Containment NR Pressure 1
N/A C-1 Cont. 451 M825-4 LM V-12 Aux.
451 M825-4 1PT-937 Containment NR Pressure.
1 N/A B-2 Cont. 426 M824-4 LM S.7-12 Aux.
426 M831-10 1PT-PC004 Containment WR Pressure 1
II.F.1 C-1 Cont. 426 M824-4 LM V-12 Aux.
426 M824-4 1PT-PC005 Containment WR Pressure 1
II.F.1 B-2 Cont. 451 M825-4 LM S.7-12 Aux.
451
- 1825 1PT-514 Steamline Pressure 1
N/A
, R13 &.7 377-Piping M833-1 LM Tunnel SE Area
. 1PT,515 Steamline Pressure 1
N/A R13 & 7 377-Piping M833-1 LM Tunnel SE Area lPT-516' Steamline Pressure 1
N/A R-13 377-Piping M833-1 1PL79JB Tunnel SE Area 1PT-524 Steamline Pressure 1
N/A R20 & 7 377-Piping M833-2 LM Tunnel SW Area lPT-523 Steamline Pressure 1
N/A R20 377-Piping M833-2 1PL77JC Tunnel SW Area
- - = ~ ~ - - - -
y.
3 Table A 3/6 R.G. 1.97, Rev. 3 & NUREG-0737 PAM INSTRUMENTS R.G. 1.97 NUREG-0737 Instr.
Instr.
Instrument No.
Service Cat.
Act. Item COL-ROW EL.
Loc. Dwg.
Location 1PT-526 Steamline Pressure 1
N/A R20&7 377-Piping M833-2 LM Tunnel SW Area
.lPT-534 Steamline Pressure 1
N/A R20&7 377-Piping M833-2 LM Tunnel SW Area
.lPT-535 Steamline Pressure 1
' N/A R20 377-Piping M833-2 1PL77JC Tunnel SW Area
. lPT-536 Steamline Pressure 1
N/A R20&7 377-Piping M833-2 LM Tunnel SW Area
.lPT-544 Steamline Pressure 1
N/A R13&7 377-Piping M833-1 LM
' Tunnel SE Area
- 1PT-545 Steamline Pressure 1
N/A R13&7 377-Piping M833-1 LM Tunnel SE Area-
=1PT-546 Steamline Pressure 1
N/A R-13 377-Piping M833-1 1PL79JB Tunnel SE Area
.1LT-930 RWST Level 1
N/A Below 379'6"-RFLG M835-3 LM RWST' WTR. Pipe
@21 Line Tunnel elLT-931 RWST Level 1
N/A BB-13 379'6"-RFLC M835-3 LM WTR. Pipe Tunnel
,1LT-932 KREr Level 1
N/A BB-13 379'6"-RFLG M835-3 LM WTR. Pipe e
Tunnel
,ILT-933 RRST Level 1
N/A AA-13 379'6"-RFLG M835-3 LM WTR. Pipe Tunnel
- 1LT-PC006 Containment Level 1
II.F.1 C-9 Cont. 377 M821-1 LH
- lLT-PC007 Containment Level 1
II.F.1 C-9 Cont. 377 M821-1 UI
.lFT-AF011 Auxiliary Feedwater Flow 1
II.E.1.2, P-13 Aux.
364 M828-9 1PL84JA
_]
)
, Table A 4/6 R.G. 1.97. Rev. 3 & NUREG-0737 i
PAN INSTRUMENTS R.G. 1.97 NUREG-0737 Instr.
Instr.
Instrument No.
Service Cat.
Act. Item COL-ROW EL.
Loc. Dwg.
Location
.lFI-AF012 Auxiliary Feedwater Flow 1
II.E.1.2 N-12 lux.
364 M828-9 1PL84JB
.1FT-AF013 Auxiliary Feedwater Flow 1
II.E.1.2 P-13 Aux.
364 M828-9 1PL84JA 1FT-AF014 Auxiliary Feedwater Flow' 1
II.E.1.2 N-12 Aux.
364 M828-9 1PL84JB
.lFT-AF015 Auxiliary Feedwater Flow 1
II.E.1.2 P-13 Aux.
364 M828-9 1PL84JA 1FT-AF016 Auxiliary Feedwater Flow 1
II.E.1.2 N-12 Aux.
364 M828-9 1PL84JB lFR-AF017 Auxiliary Feedwater Flow 1
II.E.1.2 P-13 Aux.
364 M828-9
-lPL84JA
.lFI-AF018 Auxiliary Feedwater Flow 1
II.E.1.2 N-12 Aux.
364 M828-9 1PL84JR 1RE-AR020 Containment High Range Radiation 1.
II.F.1.
F-1 Cont. 451 M825-3 LM 1RE-AR021 Containment High Range Radiation 1 II.F.1.
G-ll Cont. 451 M825-2 LM TE01-TE-65 Core Exit Temperature 1
II.F.2.
Cont.
(TE's In RX Vessel, Ref. Junction Boxes in Containment 1
II.F.2.
Cont.
1LS-CSO46A Spray Additive Tank Level 1
N/A U-13 dux.
364
.M828-10 LM ILS-CSO46B Spray Additive Tank Level 1
N/A S-12 Aux.
364 M828-10 LM 1RE-AR022A Secondary System Radiation l'
II.F.1.
Stm..
Aux. Bldg.
M833-1 LM Tun.
385'4" 1RE-AR022B Secondary System Radiation 1
II.F.1.
Stm.
Aux.. Bldg.
M833-2 LM Tun.
385'4" Secondary S' stem Radiation 1
II.F.1.
Stm.
Aux. Bldg.
M833-2 LM 1RE-AR022C y
Tun.
385'4" 1RE-AR022D Secondary System Radiation.
1 II.F.1.
Stm.
Aux. Bldg.
M833-1 LM Tun.
385'4" 1RE,AR023A Secondary System Radiaticn -
1 II.F.1.
Stm.
Aux. Bldg.
M833-1 LM Tun.
385'4" 1RE-AR0,23B Secondary System Radiation 1
II.F.1.
Stm.
Aux. Bldg.
M833-2 LM Tun.
385'4" 1RE-AR023C Secondary System Radiation 1
II.F.1.
Stm.
Aux. Bldg.
M833-2 LM Tun.
385'4" 1RE-AR023D Secondary System Radiation...
1 II.F.1.
Stm.
Aux. Bldg.
M833-1 LM Tun.
385'4" Later Neutron Flux (Currently in Containment Later Neutron Flux Procurement for 1st Refuel Outage Installation) i
=
i 1
i i
~%
'. Table A 5/6 s
R.G. 1.97, Rev. 3 & NUREG-0737 PAM INSTRUMENTS R.G. 1.97 NUREG-0737 Instr.
Instr.
Instrument No.
Se rvice
. Cat.
Act. Item COL-ROW
. EL.
Loc. Dwg.
Location Limit Switches Containment Isolation Valves Positions 1
N/A Mounted on Valves (For Valve tag's reference FSAR Table 6.2-58) 1 N/A OH lLE-RC019 Reactor Vessel Level 2
II.F.2 In RX Cont.
~
Vessel ILE-RC020 Reactor Vessel Level 2
II.F.2 In RX.
Cont.
LM Vessel IPS43J/1PS47J Containment Hydrogen 1
II.F.1 Approx.
Concentration S-17 Aux.
401 M830-5 LM 1PS44J/IPS48J Containment Hydrogen 1
II.F.1 Approx.
Concentration S-17/U-18 Aux.
401 M830-5 LM 1RE-AR024A Auxiliary Building Area 2i N/A Stm.
Lux.
381' M833-1 LM Radiation Tun.
1RE-AR024B Auxiliary Building Area 2
N/A Stm.
Aux.
381' M833-2 LM
- i. :'
Radiation Tun.
1RE-025A Auxiliary Building Area 2.
N/A Approx.
Radiation X-13 Aux. 369'6" M828-12 LM 1RE-025B Auxiliary Building Area 2
N/A Approx.
Radiation U-13 Aux. 369'6" M828-11 LM 1RE-AR026A Auxiliary Building Area 2
N/A Approx.
X-13 Aux. 383'0" M829-1 LM Radiation 1RE-AR026B Auxiliary Building Area 2
N/A Approx.
Radiation V-13 Aux. 383'0" M829-2 LM 1RE-AR027A Auxiliary Building Area 2
N/A Approx.
Radiation Y-13 Aux. 401'0" M830-1 LM 1RE-AR027B Auxiliary Building Area 2
N/A Approx.
Radiation V-13 Aux. 401'0" M830-2 LM 1PR29J/ IPR 30J Gaseous Effluent Radioactivity 2
II.F.1 Between L&M on 17 Aux.
477' M832-34 LM 2PR29J/2PR30J Gaseous Effluent Radioactivity 2
II.F.1 M-17/
N-17 Aux.
477' M832-34 LM Limit Switches Pressurizer: PORV's Position 2
II.D.3 Hbunted on Valves Limit Switches Pressurizer Safety Relief 2
II.D.3 Mounted on Valves Positions 9
9
"*"-'se-m-
..,m..
l Table A 6/6 R.G.1.97, Rev. 3 & NUREG -0737 PAM INSTRUMENTS R.G. 1.97 NUREG-0737 Instr.
Instr.
Instrument No.
Service Cat.
Act. Item COL-ROW EL.
Loc. Dwg.. Location
, Limit Switches ESW Supply to AF Valve Position 1
N/A Mounted on Valves
.lFT-CS011 Containment Spray Flow 2
N/A V-15 Aux.
346 M827-7 1PL81JA
.1FT-CS012 Containment Spray Flow 2
N/A W-15 Aux.
346 M827-7 1PL81JB Breaker Relay RCFC Hi/Lo Bkr Status
'2 N/A At Bkr
- 1EI-AP054 ESF Bus Voltages 2
N/A Aux.
451 Main Control Room IPM01J
- LEI-AP086 ESF Bus Voltages 2
N/A Aux. 451:
Main Control Room IPM0lJ 1LT-PC002 Containment Floor Drain Samp Level N/A II.F.1 B-6 Con'. 377 M821-1 LM t
1LT-PC003 Containment Floor Drain Samp Level
'N/A II.F.1 B-7 Cont.. 377 '.'
M821-1 LH 9
?
t
~
e 0
N