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.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
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Director of Nuclear Reactor Regulation fg4 *
- ATTN: Mr. John F. Stolz, Chief Branch No. 1
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3 Light Water Reactors Project U. S. Nuclear Regulatory Commission 6-
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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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Mr. John F. Stolz - NRC Page 2 April 2, 1976 I
G01-76-192 2.
_ECCS FAC Analysis for Partial Loop Operation breaks during partial loop operation by the firs 1976.
ae we have found it necessary to reschedule this an of I
submittal to the NRC in the second quarter of 1977.
1 be before the submittal of.the WMP-1/4 FSAR wh i
This will scheduled to be submitted to the NRC for the acceptance revie y
in September 1978.
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 Coolin g
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 and indicatiopSA the control rocm and that the flow in the bypass lines n in be indicated in the control room.
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In Reference 3 we replied that the plant operating staff would have several days before they would need to initiate long-term cooling and, therefore the bypass valves should be accep, table. local manual operation of provide additional justification for this position.We committed to acceptable to manually preset the bypass valv flow of 40 gpm.
to startup, there would be no need for additional adjust during long-term cooling and, therefore, no need for control ent 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.
have two isolation valves inside Containment.as indica
- However, 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
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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
~
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
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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
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review on February 10, 1976.
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
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EG Ward - B&W TH Cox - NRC a
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ATTACH!!E!1T
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B&W.WNP-1/4 INTERFACES ITE!! 5 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 Section 5.9 Yes IEEE-334 9
VI Cables and Raceways to be separated by 1ECE-364
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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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5.4
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