ML20249B445

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Rev 0 to Calculation C15.0.3270, Fuel Pool Cooling He E206A & E206B GIP Evaluation
ML20249B445
Person / Time
Site: Pilgrim
Issue date: 01/04/1996
From: Dyckman J, Pitts C, White T
BOSTON EDISON CO.
To:
Shared Package
ML20249B442 List:
References
C15.0.3270, C15.0.3270-R, C15.0.3270-R00, NUDOCS 9806230121
Download: ML20249B445 (24)
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{{#Wiki_filter:- _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ 0 Boston Edison CALCULATION COVER SIIEET PILGRIM NUCLEAR POWER STATION lSh 1 of 24 l CALC No C15.0.3270 REV.0 FILE NO. SR @ R-TYPE NSR O Subject Fuel Pool Cooline HE E206A & E206B GIP Evaluation Preliminary Calc. O Finalization Discipline Division Manager: N IT Due Date: //9hh Approval /s/; lh Date: Final Calc. V '/ Independent Reviewer:, /S/OMAfM6 5 RYStatementattached @ Page(s) By _LG. Dkk) nan. Date Ch'k'd U /) /. Date Agrpxl ' /S/ / /S/ U f ( l \\ This calculation evaluates the Fuel Pool Cooling IIE scismic ddequacy u(san Generic screening methodology, 1.0 Problem Statement 2.0 Summary of Results 3.0 Method of Solution 40 References 5.0 Calculation Generic Implementation Procedure Section 7.4 Evaluation Walkdown Observations Conclusion Attachments: A. Bechtel Calculation 10394-114-C7 (9 sheets) B. Independent Design Verification Record (3 sheets) C. Preliminary Evaluation Checklist (2 sheets) This design analysis DOES O, DOES NOT @ require revision to design docuruents. affected Design Documents: 4FDC IS O,IS NOT @ Required. A dafety Evaluation IS 0. IS NOT @ Required. l This design analysis DOES O, DOES NOT @ affect the piping analysis index (PAI). If the pal is affected, initiate a sevision to Calculation M561. l Minor revisions made on pages of this calculation. See next revision. l Replaces Calc No.: Voided by Calc No.: O Or Attached Memo f NESD 3.05 Rev. (9 JGD/htG5316 9806230121 990615~ PDR ADOCK 05000293 ( P PDR

Bostors Edimors CALCULATION SHEET Calculation #: C15.0.3270 Revision: 0 Date: 8/95 Prepared by: J.G. Dyckman Sheet 2 of 24 Checked by: W'DjotdfeWu SR E NSR 0 1.0 PROBLEM STATEMENT A seismic adequacy evaluation is required for the Fuel Pool Cooling Heat Exchanger E-206A and E-206B to address USI A-46 concerns. 2.0

SUMMARY

OF RESULTS The Fuel Pool Cooling Heat Exchangers E-206A and E-206B are outliers because they are flexible and do not have sufHcient capacity to meet the SPA requirement per the screening method, Section 7.4.2 of the Generic Implementation Procedure. Nevertheless, the detailed analyses presented herein shows the Fuel Pool Cooling HE's meet GlP requirements based on computed SA's, and no further action is required. 3.0 MLillOD OF SOLUTION A seismic adequacy evaluation is performed for heat exchangers using the GIP screening methodology of Section 7.4.2. Seismic demand is based on computed spectral accelerations (SA's) which include sensitivity variations (120%) recommended by Ref. 5.

4.0 REFERENCES

1. Drawings MI1-22-3, MI1 2-5, C100, C101 and Stress Isometrics 623,624,634-2,635-2,691 and 693 2. Generic Implementation Procedure, Rev. 2 3. Specification C-Il4 4. SEWS for E206A and 206B 5 EPRI NP-5228-SL, Rev.1, Vol. 4 6 BECo Calculation C15.0.1811 NESD 3.05 Rev.19 JGD/hl/95316

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Calcuttion C15.0.3270 Attachment B Page.l. of 3_ INDEPENDENT DESIGN VERIFICATION RECORD (IDVR) I. Instructions to inQendent personnel Design Documents C15.0.3270 0 fuel Pool Coolina HE E206A & B (Document No.) (Rev.) (Document Title) Design verification should be done in accordance with ANSI N45.2.ll, Section 6, as amended by Reg. Guide 1.64, Rcv.1. Verification Methods to be used; Document (s)"Q" Level: Design review Q O Alternate or simplified calculations O FF-Q O Qualification Testins-0 Non-Q Special Instructions m h-I O& ff Div. 51anager V Date # 11. Verification Documentation: Methods Used: Design review (attach any documentation) O Alternate or simplified calculations (attach calculations) O Qualification Testing (attach Test Report) Design Document Acceptable: YES E No O If not acceptable,.3 c reasons or provide comments on Exhibit 3.06-B. In ependen Design Verif c ck com ! cted b ~ independent Reviewer Datd / d Acknowledgement of verifi:ation: I ~ U Date ' / ivision Manager 111. Resolution of conunents: Conunents resolved (See Exhibit 3.06-b): f{__ lD I Cognizan . Engineer Date \\ Action taken makes design document acceptable rL L r Pds ahnks ~ Independent Reviewer ' Date Exhibit 3.06-A Rev. 7 JGD%Lm316

Calculation _C15.0.32 70 Attachment B Pr:ge,2, of 3_ O so roaed'=aa oESioN REVIEW CHECKLIST ~ YES NO N/A 1. Where design in puts correctly selected and incorporated into the design d ocument? 2. Are assumptions necessary to perform the design adequately E described and reasonable? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed? 3. Are the appropriate quality assurance requirements specified? 4. Are the applicable codes, standards and regulatory M requirements including issues and addenda properly identified and are their design requirements met? 5. Has applicable constmetion and operating experience been Q considered? 6. Has design interfacu with other functional units requirements been utilized? 7. Was an appropriate design method used? E j 8. Is the design document reasonable compared to the design input? 9. ! re the specified parts, egapment and processes suitable O O m for the required application?

10. Are the specified materials compatible with each other and O

E the design environmental conditions to which the material will be exposed? 'l1. Have adequate suaintenance features and requirements been specified?

12. Are accessibility and other design provisions adequate for performance of needed maintenance and repair?
13. Has adequate accessibility been provided to perform the in-service inspection expected to be required during plant lifetime?

I L Has the design properly considered radiation exposure to O E the public and plant personnel? Have ALARA considerations been addressed?

15. Are the acceptance criteria incorporated in the design documents sufficient to allow verification that design requirements have been satishetorily accomplished?
16. Have sufficient installation details and/or instructions, including specification of applicable special processes, been included in the design output?

Exhibit 3.06-B Rev. 7 samumis j

Cdculation C15.0.3270 Attachment B Page.3. cf 3_ h Bostors Edisora DESIGN REVIEW CHECKLIST (Continued) YES NO N/A

17. Have adequate pre-operational and subsequent periodic test O

requirements specified (including 1st)?

18. Are adequate handling, storage, cleaning and shipping S

I requirements specified?

19. Are adequate identification requirements specified?

l

20. Are requirements for record preparation review, approval, O

B retention, etc. adequately specified? l 21 Have all of the potentially applicable design considerations l been correctly evaluated for applicability to the specific l' case and have the a aplicable considerations been correctly i a.1d completely dea t witi.') l

22. Have the problems with this design, known from prior O

i applications, been considered and resolved? l'

23. Have relevant design basis documents such as Design

. Specifications, FSAR, Tech. Specs., and the Fire Protection . Review Report been researched and referenced in the design inputs and safety evaluation?

24. For modifications to existing components, check that the O

E original manufacturers estimated impact on the existing components that will be modified is included, or a statement indicating why tSe information could not be obtained, or was not necesary to be obtained. l

25. Are the Section 's'I Repair / Replacement Plant Requirements O

l specified (refer to NOP 83El, Nuclear Engineering i Department Work Instruction 409, or Exhibit 3.02-BB). COMMENTS RESOLUTION MINM. CO M M u/Tb tutoGP;M T7r 0 INTD VAboas CALC SG(not).$, l Submitted ,I /2!2")/hE Resolved Date Date i i Exhibit 3.o6-B Rev. 7 I kid'hkM5316

Calculati:n C15.03270 Attachment C i l Page l. of 2 _ RTYPE A9.02 PRELIMINARY EVALUATION CHECKLIST I 1. IDENTIFICATION: Document Number: C15.0.3270 Revision 0 t l l Fuel Pool Cooling HE E-206A & B GIP Evaluation t l 2. CLASSIFICATION: Yes No a. Does the proposed change involve Q listed equipment? O Yes O No b. For a new procedure, Temporary Procedure, or major revision; does the Procedure contain procedural steps or requirements in the FSAR? If yes, identify FSAR sections. N/A Oyes %No c. Is this a new procedure or Temporary Procedure that is Fire Protection Program related or a major revision that makes an existing procedure l Fire Protection Program related? l NIA l 3. PRELIMINARY EVALUATION: l O Yes @ No a. Would this modify piant characteristics or procedural steps described j in the FSAR7 If yes, identify section: t O Yes @ No b. Does this affect the design of systems, structures or components l described in the FSAR? O Yes @ No c. Does this af'- :t the function of systems, structures or components ) described in the FSAR7 O Yes- @ No d. Does this affect the method of performing the function of systems, structures or components described in the FSAR7 . O Yes @ No e. Does this indirectly affect the capability of safety related systems, structures or components Cscribed in the FSAR to perform their functions? 1 O Yes @ No f. Does this create a new test not described in the FSAR that could ) affect plant safety? Exhibit 4 t NOP83E5 Rev. 7 l Janw953is

Calculation C15.0.3270 Attachment C Page.2. of 2 _ PRELIMINARY EVALUATION CHECKLIST (Continued) O Yes @ No ' g. Would this change modify assumptions used in the accident analyses described in FSAR Chapter 147 If yes, identify sections: 0 Yes @ No h. Does this change affect the ability of a system required to achieve and maintain safe shutdown in an event of a fire? O Yes @ No I. Does this change affect a requirement of, or niajor commitment to, 10CFR50 Appendix R7 0 Yes @ No J. Does thit ' hange affect a requirement of IE Clicular 80-18 (for c Radioactive Waste Systems)? O Yes @ No k. Could this affect the function of systems or components required for compliance with the Limiting Conditions for Operation in the Technical Specifications? O Yes @ No I. In the judgment of the evaluator, is a Safety Evaluation required? If the answer to any questions in Part 3 is "Yes", then a Safety Evaluation is required prior to implementation. Check the appropriate block and provide any explanatory comments below; i 4. SAFETY EVALUATION RE IRED 7 0 Yes No s 5. PREPARED BY: iA / Principal Enaineer DATE: 8/10/95 ' " '/ Title ' Civil DM DATE: /kfD APPROVED BY Title / Exhibit 4 NOP83E5 Rev. 7 JGDM/95316 j}}

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