ML17290A558

Requests Response to Encl Request for Addl Info Re GL 92-01, Reactor Vessel Structural Integrity within 60 Days of Ltr Date

ML17290A558
Person / Time
Site:	Columbia
Issue date:	07/21/1993
From:	Clifford J Office of Nuclear Reactor Regulation
To:	Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
GL-92-01, GL-92-1, TAC-M83527, NUDOCS 9308110281
Download: ML17290A558 (8)

Text

July 21, 19930 Docket No. 50-397 Hr. J.

V. Parrish (Hail Drop 1023)

Assistant Managing Director, Operations Washington Public Power Supply System'.

0.

Box 968

Richland, Washington 99352-0958

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-01, "REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NO. H83527)

You provided a response to Generic Letter (GL) 92-01 in a [[letter::GO2-92-158, Forwards Rev 0 to COLR 92-8, Washington Nuclear Plant 2 Cycle 8 Core Operating Limits Rept. Siemens Power Corp Completed Reanalysis of Feedwater Controller Failure Transient for Cycle 8 & MCPR Operating Limits|letter dated July 6, 1992]].

We have completed our review of your response.

Enclosed is a request for additional information that we need to complete our evaluation of your compliance with 10 CFR Part 50 Appendixes G and H.

You are requested to provide your response within 60 days of the date of this letter.

Please contact me if you have any questions.

This requirement affects (9 or fewer) respondents and, therefore, is not subject to Office of Management and Budget review under P.

L.96-511.

Sincerely, Originai signed by James W. Clifford, Senior Project Manager Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/enclosures:

See next page DISTRIBUTION:

Docket File JRoe JClifford

ACRS, P315 (10)

NRC S. Local PDRs EAdensam DFoster-Curseen

KPerkins, RV PDV Reading Fi1 e Tguay

OGC, 15B18 OFFICE PDV LA 6

PDV P

PDV D

IIANE DAIE DFoster-Curseen O'0 93 JClifford:mc a ~93 TOuay 0 /4

/93 OFFICIAL RECORD COPY DOCUMENT NAME:

WNP83527.RAI

'93081 1028i, I930721 Wi'DR ADQCK 05000397, P

PDR~

fl5lg FI,'ggP ~TQ~

C~

I ii I

- i'G=L~ZB '

<pa Ra'Co 0

A.n p

0

~>>*<<~

I t~~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Ouly 21, 1993 Docket No. 50-397 Mr. J.

V. Parrish (Hail Drop 1023)

Assistant Managing Director, Operations Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352-0958

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-01, "REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NO. H83527)

You provided a response to Generic Letter (GL) 92-01 in a [[letter::GO2-92-158, Forwards Rev 0 to COLR 92-8, Washington Nuclear Plant 2 Cycle 8 Core Operating Limits Rept. Siemens Power Corp Completed Reanalysis of Feedwater Controller Failure Transient for Cycle 8 & MCPR Operating Limits|letter dated July 6, 1992]].

We have completed our review of your response.

Enclosed is a request for additional information that we need to complete our evaluation of your compliance with 10 CFR Part 50 Appendixes G and H.

You are requested to provide your response within 60 days of the date of this letter.

Please contact me if you have any questions.

This requirement affects (9 or fewer) respondents and, therefore, is not subject to Office of Management and Budget review under P.

L.96-511.

Sincerely,

Enclosure:

As stated cc w/enclosures:

See next page mes W. Clifford, Senior Project Manager Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Hr. J.

V. Parrish Washington Public Power Supply System WPPSS Nuclear Project No.

2 (WNP-2)

CC:

Hr. J.

H. Swailes WNP-2 Plant Manager Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352-0968 G.

E.

C. Doupe, Esq.

(Hail Drop 396)

Washington Public Power Supply System 3000 George Washington Way P. 0.

Box 968

Richland, Washington 99352-0968 Hr. Warren Bishop, Chairman Energy Facility Site Evaluation Council P. 0.

Box 43172 Olympia, Washington 98504-3172 Hr. Alan G. Hosier (Hail Drop PE20)

WNP-2 Licensing Manager Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352-0968 Hr.

G.

C. Sorensen (Hail Drop PE20)

Regulatory Programs Manager Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352-0968 Regional Administrator, Region V

U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Chairman Benton County Board of Commissioners P. 0.

Box 190

Prosser, Washington 99350-0190 Hr.

R.

C. Barr U. S. Nuclear Regulatory Commission P. 0.

Box 69

Richland, Washington 99352-0968 H. H. Philips, Jr.,

Esq.

Winston 5 Strawn 1400 L Street, N.W.

Washington, D.C.

20005-3502

4l

Enclosure REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 92-01, "REACTOR VESSEL STRUCTURAL INTEGRITY" The following requests are referenced to the corresponding question from GL 92-01.

uestion 2a Your response to GL 92-01 indicates that the initial upper-shelf energy (USE) values for all beltline materials are not known.

A topical

report, NEDO-32205 entitled "BWR Owners'roup Topical Report on Upper Shelf Energy Equivalent Margin Analysis" regarding beltline materials with low USE, was submitted by General Electric Corporation on April 30, 1993.

You are requested to commit to using this topical report as your licensing bases to demonstrate that all reactor vessel beltline materials that do not have measured USE will meet the requirements of 10 CFR Part 50, Appendix G.

uestion 2b 2.

Your response to GL 92-01 indicates that values for the initial RT and chemistry data for beltline materials can be found in WNP-2's SAR Section 5.3.1.5.2.2.

The initial RT>>y values for most beltline welds are not specified in the FSAR, rather only the highest RT>>> value is given.

Provide either the data (the initial RT>>y and chem~istry data) for each beltline weld, or the data and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication

process, and material specification to establish the generic initial RT>> values for the beltline welds.

The copper and nickel values for weld RACOlNMM are

.09% and

.93%,

respectively, in the FSAR, which differ from the corresponding values of

.08% and

.80% listed in the latest pressure/temperature limits submittal (dated October 27, 1989).

Please reconcile this discrepancy.

h.

l 1

I i,

'