ML20138D922
| ML20138D922 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/28/1997 |
| From: | Brinkman D NRC (Affiliation Not Assigned) |
| To: | Cross J DUQUESNE LIGHT CO. |
| References | |
| TAC-M96303, NUDOCS 9705010297 | |
| Download: ML20138D922 (4) | |
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April 28, 1997 1-Mr. J. E. Cross President-Generation Group t
Duquesne Light Company Post Office Box 4 Shippingport. PA 15077
SUBJECT:
SECOND REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING PROPOSED UPDATE OF THE PRESSURIZED THERMAL SHOCK ASSESSMENT FOR BEAVER VALLEY POWER STATION. UNIT NO. 1 (BVPS-1) REACTOR VESSEL (TAC NO. M96303) i
Dear Mr.. Cross:
By letter dated March 14, 1997. Dusquesne Light Company (DLC) submitted a response to our RAI of February 10, 1997. regarding DLC's reassessment of 3ressurized thermal shock (PTS) analysis for the BVPS-1 reactor vessel which lad been submitted by letter dated August 2. 1996. The NRC staff has reviewed DLC's M5rch 14, 1997, submittal and has determined that further clarifying information is required to complete our review of this issue. The additional-information that is required is described in our enclosed RAI.
DLC is-requested to provide this additional information within 30 days of receipt of this letter.
Should you have any question on this matter, please contact me on (301) 415-1409.
Sincerely.
(Original signed by)
Donald S. Brinkman. Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
RAI cc w/ encl:
See next page
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WASHINGTON D.C. 20066 4 001 April 28, 1997 Mr. J. E. Cross President-Generation Group Duquesne Light Company Post Office Box 4 Shippingport. PA 15077 i
l
SUBJECT:
SECOND REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING PROPOSED UPDATE OF THE PRESSURIZED THERMAL SHOCK ASSESSMENT FOR BEAVER VALLEY POWER STATION. UNIT NO. 1 (BVPS-1) REACTOR VESSEL (TAC NO. M96303)
Dear Mr. Cross:
l By letter dated March 14. 1997. Dusquesne Light Company (DLC) submitted a l
response to our RAI of February 10. 1997. regarding DLC's reassessment of pressurized thermal shock (PTS) analysis for the BVPS-1 reactor vessel which had been submitted by letter dated August 2,1996.
The NRC staff has reviewed DLC's March 14, 1997, submittal and has determined that further clarifying information is required to complete our review of this issue. The additional information that is required is described in our enclosed RAI.
DLC is requested to provide this additional information within 30 days of receipt of this letter.
l Should you have any question on this matter, please contact me on (301) 415-1409.
l Sincerely, l
f $Uh--<,--
l Donald S. Brinkman. Senior Project Manager Project Directorate I-2 i
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Docket No. 50-334
Enclosure:
RAI cc w/ encl: See next page l
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J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2 cc:
Jay E. Silberg, Esquire Bureau of Radiation Protection Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of j
2300 N Street. NW.
Environmental Resources Washington. DC 20037 ATTN:
R. Barkanic Post Office Box 2063 R. K. Brosi Manager Harrisburg, PA 17120 Nuclear Safety Department (BV-A)
Duquesne Light Company j
Beaver Valley Power Station Mayor of the Borrough of PO Box 4 Ship ngport Shippingport, PA 15077 Post Of ce Box 3
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Commissioner Roy M. Smith West Virginia Department of Labor Regional Administrator. Region I Building 3, Room 319 U.S. Nuclear Regulatory Commission l
Capitol Complex 475 Allendale Road Charleston, WVA 25305 King of Prussia, PA 19406 John D. Borrows' Resident Inspector Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport, PA 15077 Columbus, OH 43266-0573 Director, Pennsylvania Emergency Duquesne Light Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport PA 15077 ATTN:
S. C. Jain Vice President l
Ohio EPA-DERR Nuclear Services (BV-A)
ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 Dr. Judith Johnsrud l
National Energy Committee l
Sierra Club-433 Orlando Avenue State College, PA 16803 i
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l SECOND RE0 VEST FOR ADDITIONAL INFORMATION REGARDING AUGUST 2. 1996 PRESSURIZED THERMAL SHOCK (PTS) REASSESSMENT BEAVER VALLEY POWER STATION. UNIT NO. 1 (BVPS-1) l DOCKET N0. 50-334 The NRC staff has reviewed the information that was submitted in the March 14, 1997 response to the staff's RAI dated February 10, 1997.
Based on this information and the information provided in Duquesne Light Company's (DLC) original submittal (August 2.1996), the staff requests that DLC supplement DLC's PTS evaluation to address the following issues.
)
1.
It is the NRC staff's position that DLC should use 34 F for the l
margin term when evaluating lower shell plate B-6903-1 rather than the i
value of 29.1*F ia-d in WCAP-14543.
The use of 34 F for this margin term is consistent with the value previously accepted by the staff in DLC's previous PTS evaluation.
2.
Recently, information provided from a French source has indicated l
that core barrel support rings may be shadowing surveillance capsules and the dotimeters within them, in some RPV surveillance programs.
The NRC staff has begun to discuss this issue with Westinghouse.
Westinghouse staff members are aware of the NRC staff's concerns that, if these su) ports are not modelled correctly. this may lead to deviations Jetween measured and calculated neutron fluence values.
Assess whether such a problem may exist for the measured and calculated fluence values in the case of BVPS-1 and provide drawings of the reactor vessel internals which show the relative location of the baffle radial support plates (baffle formers), the surveillance s)ecimen capsules, and the dosimeters and Charpy impact specimens within tie surveillance capsules.
l 3.
The NRC staff has established the position of not accepting adjustments to calculated neutron fluence values based on the use of l
dosimetry data and the FERRET code (for reference, see the staff's i
safety evaluation on the PTS reassessment for Palisades. December 20, 1996).
Perform DLC's PTS reassessment based on calculated fluence values for determining:
(1) surveillance capsule fluences i
(2) the chemistry factors from BVPS-1 surveillance results, and (3) the E0L fluences of the RPV plates and welds.
Recognize that the NRC staff ex)ects that this reevaluation will include any changes which result from D_C's investigation into the need to address the core baffle radial support plates raised in #2 above.
If remodelling and recalculation is necessary, the staff requests that DLC submit a schedule for resolution of this issue within 30 days of receipt of this letter.
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