ML20198G212
| ML20198G212 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 04/02/1976 |
| From: | Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20198G202 | List: |
| References | |
| CON-WNP-1114 GO1-76-192, NUDOCS 8605290292 | |
| Download: ML20198G212 (5) | |
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'( ~p Washingto. Public Power Supply System W y[,/74
,': ~y A JOINT OPERATING AGENCY
._ y . " g P.p.een968 sooo cro. WasMaNOTon WAy RicMLaMo. WASHINGToM 99352 PMoNtt503) 946 1611 Docket Nos. 50-460 April 2,1976
. 50-513 G01-76-192 W A.
/f Director of Nuclear Reactor Regulation ,
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- ATTN: Mr. John F. Stolz, Chief Light Water Reactors Project Branch No. 1 -
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3 U. S. Nuclear Regulatory Commission 6- $4..,, 8 g g Washington, D. C. 20555 %h d'c,
Subject:
WPPSS i;UCt. EAR PROJECTS i;05.1 & 4 OUTSTAliDIllG f;RC SAFETY REVIEU ITEMS N '
References:
- 1) Letter, NO Strand, WPPSS, to Angelo Giambusso, NRC,
" Submittal of Additional ECCS Information," dated July 25, 1975.
f-2) Letter, Kenneth E. Suhrke, B&W, to John F. Stolz,f;RC, dated March 30, 1976. p
- 3) Letter, NO Strand, WPPSS, to Roger Boyd, f;RC, y
" Additional ECCS Information," dated September 26,19K.
% 4) Letter, Kenneth E. Suhrke, B&W, to John F. Stolz, NRC, dated January 23, 1976.
Dear Mr. Stolz:
This letter addresses outstanding safety review items for WNP-1/4 that were to be addressed in late 1975 and early 1976.
- 1. Passive Failure Analysis for Long-Term Coolina In Reference 1 we committed to provide an evaluction of the potential consequences of passive failures during long-term cooling. In Reference 2 B&W submitted this evaluation.
Reference 2 is hereby incorporated by reference into the appli-cations for construction permits and operating licenses for WNP-1/4. It is recognized that we will need to address some balance of plant considerations for passive failures during long-term cooling. He would prefer to address these items after the NRC review of the B&W submittal has been completed.
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PageJohn 2 F. Stolz - NRC I ' April 2, 1976 G01-76-192 2.
_ECCS FAC Analysis for Partial Loop Operation .
breaks 1976. during partial loop operation of ae by the firs I
we have found it necessary to reschedule this an ,
1 submittal to the NRC in the second quarter of 1977.
i This will be scheduled in before September 1978.
the submittal of.the WMP-1/4 to be submitted to the NRC for the acceptance y FSAR revie wh In PSAR Amendment 20 we complied with the NRC's request fo a technical specification limitation prohibiting partial (PSARSubsection16.3.1.2). loop operation until this analy
. 3.
Justification for Manual Operation During Lone-Term g Coolin The Staff has requested that the throttling valves in the b line around MV21A and MV21B (
Reference:
ypass Amendment 20) be motor operated with control n inand indicatiopSA the control rocm and that the flow in the bypass ,also lines be indicated in the control room.
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- In Reference 3 we replied that the plant operating staff would long-term have several cooling days before they would need to initiate and, therefore the bypass valves should be accep, table. local manual operation of .
provide additional justification for this position.We committed to acceptable flow of 40 gpm. to manually preset the bypass valv to startup, there would be no need forentadditional adjust during long-term cooling and, therefore, no need for control and indication in the control room or flow indication in t control room.
result in a departure from General Design Criterion 5 requires an isolation valve outside Containment.However, have two isolation valves inside Containment.as indica of presetting the bypass valves before startup in
- adjusting the valves immediately before long-term cooling.
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Mr. John F. Stolz - NRC .
April 2, 1976 Page 3 ,
G01-76-192
- 4. Mark C R&D Test Results In the WNP-1/4 Safety Evaluation Report (PP l-12, 4-4, and 4-9),
it is stated that the Mark C fuel assembly R&D program will be completed in late 1975. The current B&W schedule is to complete mechanical testing by September 1977 and complete critical heat flux testing by September 1978. BAW-10097PA, Rev. 2, transmitted to the NRC on January 28, 1976, is B&W's most recent formal submittal for the Mark C R&D program. This report has been approved by the NRC. On February 18, 1976, B&W submitted the first status update for the Mark C R&D program.
- 5. Application of Regulatory Guide 1.75 to B&W Supplied Safety and Protection System Cabinets -
In Supplement 2 to the Safety Evaluation Report, P. 7-3, and in our response to NRC Question 7.30, we cc=nitted to provide additional information concerning the application of Regulatory Guide 1.75 to the B&W supplied safety and protection system cabinets. In Reference 4 B&W provided this information directly to the NP.C. Reference 4 is hereby incorporated by reference into the applications for construction permits and oper,ating licenses for WNP-1/4. .
I Reference 4 includes several statements concerning the need for the balance of plant. electrical and instrumentation and control design to satisfy certain requirements. The attachment .
to this letter addresses each of these statements. The attachment shows that in all cases the WNP-1/4 design satisfies the B&W criteria and complies with Regulatory Guide 1.75.
- 6. Electrical Separation Test Results for RTD's
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In Supplement 2 to the Safety Evalution Report, P. 7-4, and in our response to NRC Question 7.30, we committed to provide the electrical separation test results for. dual element RTO's in the last quarter of 1975. Because of a delay in the procurement of these sensors, we have found it necessary to reschedule this submittal for September 1976.
- 7. RPS-II Single Failure Analyses
. In our response to NRC Question 7.34, we committed to the submittal of a B&W topical report providing single failure analy,ses for RPS-II, ESFAS, the reactor trip switch and the trip portion of the
,CRDCS by December 15, 1975.
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Mr. John F. Stolz - NRC April 2,1976 Page 4 -
G01-76-192 B&W has the position that these analyses should not be performed until they have first developed a design standard for the applica-tion of Regulatory Guide 1.75 and have then discussed this standard with the NRC. The B&W standard has been defined, and the next step is to review it with the NRC.
The current schedule for these analyses-is to begin by September 1976 with a completion date of September 1977. .
- 8. Submittal of Parts 2 and 3 to BAW-10082 Section 7.8 of the Safety Evaluation Report indicates that the submittal of Parts 2 and 3 to BAW-10082 (environmental test methods and general methodology) is scheduled for the third quarter of 1975.
Part 2 has been submitted to the NRC and has been rejected.
. B&W believes that the report was rejected because it lacked acceptance levels and test results. It was, and remains, BSW's intent to provide acceptance levels and test results in a later topical report.
Part 3 was submitted to the NRC in draft form for preliminary -
review on February 10, 1976.
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Very truly yours, 4
D. L. RENBERGER" Assistant Director Generation & TeclinW6gy DLR:AGH:km ,
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cc: CR Bryant - BPA .
JR Schaieder - VE&C '[1 -
EG Ward - B&W TH Cox - NRC
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ATTACH!!E!1T - . '
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' ITE!! 5 i 8 B&W .WNP-1/4 INTERFACES Ua. Paragraph Deccription of Interiace IEEE or WSP'1/4 R; arks .
Reference R.G. Ref. Comply?
1 II.- D -3 RB Pressure tap locations by customer (WPI'SS)
IEEE 384 Yes Section 518 2 II 4 Sensing line routes by customer,reconnen.1 separation er barriers N/A Yes
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3 II -D Separate IICC's for ESEAS actuated equip- . IEEC-334 ment Para. 5.4.2 Yes See PSAR rigure S.3-4 4 III 6 RC111 Power !!onitors(by custcmer) cach R. G. 1.75 output to 4 RPS channels. Outputs must Rev. 1 Yes Drawing avillable on request be separa ted.
5 III - D -7 See Item 2 above 6 III -D CiiD Trip Breakers to bc Iccated in Category I Structurc N/A Yes Sec PSAP.1.gure 1.2-4 7 IV - B -10 See Itea 2 above 8 IV .D SRCI controls separated by customer ,
IEEE-334 -
Section 5.9 Yes .
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9 VI Cables and Raceways to be separated by 1ECE-364 ,
customer Section 5.1 Yes See psan 1 tra. 8.3.3 end Appendin fi.
10 VL1 ton IE cchics should not be run in EPA's . I EEE-384
- with IE cables. IE-EPA's 'should bc Section 4 Yes Sec PSA:1 l igure 8.3 - 7.
physically separated from non-IE EPA's.
11 VIII Four D-C supplica and tuo dicsci power IEEE-384 Yes Sec PSA;i~5: ras. 8.1.3.4 and courtes aliould be supplied. ,
Sections 8.3.2.4 si i rig. 8.3-7..
. 5.2, 5.3,
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