ML20134K161
| ML20134K161 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/10/1997 |
| From: | Brinkman D NRC (Affiliation Not Assigned) |
| To: | Cross J DUQUESNE LIGHT CO. |
| References | |
| TAC-M96303, NUDOCS 9702130163 | |
| Download: ML20134K161 (5) | |
Text
. _ _. - _ _ _ _ _ _ _. _ _ _ _ _. _ _. _ _ _ _. _. _ _ -, _ _ _. - _.
-i i
February 10, 1997 i
Mr..J. E. Cross i
l President-Generation Group Duquesne Light Company
/Mj j
i Post Office Box 4 l
l Shippingport, PA 15077 n
j
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING PROPOSED UPDATE 0F THE PRESSURIZED THERMAL SHOCK ASSESSMENT FOR GEAVER VALLEY POWER STATION, UNIT NO. 1 (BVPS-1) REACTOR VESSEL (TAC NO. M96303) j
Dear Mr. Cross:
j By letter dated August 2, 1996, Duquesne Light Company (DLC) submitted a reassessment of DLC's pressurized thermal shock (PTS) analysis for the BVPS-1 reactor vessel in accordance with the requirements of 10 CFR 50.61. This submittal was vquired because DLC had obtained updated information which affected this assessment. The NRC staff has begun its review of the August 2, 1996, submittal; however, we have determined that additional information is i
required for us to complete our review.
The additional information that is i
required is described in our enclosed RAI. 'DLC is requested to provide its response to this RAI within 30 days of receipt of this letter for us to i
complete our review within a timely manner.
~
i Should you have any questions on this matter, please contact me on
]
(301) 415-1409.
]
l Sincerely, i
Original signed by t
Donald S. Brinkman, Senior Project Manager l
Project Directorate I-2 Division of Reactor Projects - 1/II Office of. Nuclear Reactor Regulation i
Docket No. 50-334
Enclosure:
RAI cc w/ enclosure:
See next page gg gg gy nrcraraur m.
(DocketFile3 OGC, 0-15B18 PUBUC ACRS, TWF
}l PDI-2 r/f WPasciak, RI SVarga BElliot
_ )g\\
j JZwolinski MMitchell 1
JStolz M0'Brien DBrinkman 0FFICE PDI-2/PM rff PD112dA POI-2/D NAME DBrinkman:c MdNe'n JS'fM z.
DATE 2 /10/97 h/@/97 L/fD/97 0FFICIAL RECORD COPY DOCUNENT NAME:
3V96303.RAI 13003*5 97o21ao16a 97o21o PDR ADOCK 05oo0334 p
49 p
k UNITED STATES l.
s j
NUCLENA REGULATORY COMMISSION f
WA8HlNGTON, D.C. 20666 0001 l
%,,, y February 10, 1997 Mr. J. E. Cross President-Generation Group Duquesne Light Company Post Office Box 4 Shippingport, PA 15077
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING PROPOSED UPDATE OF THE PRESSURIZED THEP, MAL SHOCK ASSESSMENT FOR BEAVER VALLEY POWER STATION, UNIT NO. 1 (BVPS-1) REACTOR VESSEL (TAC NO. M96303)
Dear Mr. Cross:
By letter dated August 2, 1996, Duquesne Light Company (DLC) submitted a reassessment of DLC's pressurized thermal shock (PTS) analysis for the BVPS-1 reactor vessel in accordance with the requirements of 10 CFR 50.61. This submittal was required because DLC had obtained updated information which affected this assessment. The NRC staff has begun its review of the August 2, 1996, submittal; however, we have determined that additional information is required for us to complete our review. The additional information that is required is described in our enclosed RAI. DLC is requested to provide its response to this RAI within 30 days of receipt of this letter for us to complete our review within a timely manner.
Should you have any questions on this matter, please contact me on (301) 415-1409.
Sincerely, cwYk. $ $W 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/ enclosure:
See next page 1
i 4
)
1 J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2 l
cc:
Jay E. Silberg. Esquire Bureau of Radiation Protection 4
Shaw. Pittman. Potts & Trowbridge Pennsylvania Department of a
2300 N Street. NW.
Environmental Resources Washington. DC 20037 ATTN:
R. Barkanic Post Office Box 2063 l
l R. K. Brosi. Manager Harrisburg, PA 17120 Nuclear Safety Department (BV-A) j Duquesne Light Company i
Beaver Valley Power Station Mayor of the Borrough of PO Box 4 Shippingport Shippingport. PA 15077 Post Office Box 3 Shippingport. PA 15077 Comissioner Roy M. Smith West Virginia Department of Labor Regional Administrator. Region I i
Building 3. Room 319 U.S. Nuclear Regulatory Commission Capitol Complex 475 Allendale Road Charleston. WVA 25305 King of Prussia. PA 19406 a
l John D. Borrows Resident Inspector l
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 i
Director. Pennsylvania Emergency Duquesne Light Company i
Management Agency Beaver Valley Power Station 4
Post Office Box 3321 PO Box 4 Harrisburg. PA 17105-3321 Shippingport. PA 15077 i
ATTN:
S. C. Jain. Vice President Ohio EPA-DERR Nuclear Services (BV-A)
ATTN: Zack A. Clayton Post Office Box 1049 l
Columbus OH 43266-0149 l
Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College PA 16803 I
k
i l.
1 J
}
RE00EST FOR ADDITIONAL INFORNATION REGARDING i
AUGUST 2. 1996 PRES $URIZED THERNAL SH0CK (PTS) REASSESSNENT BEAVER VALLEY P0NER STATION. UNIT N0. 1 (BVPS-1) l
]
DOCKET N0. 50-334 In reviewing the PTS reassessment submitted by Duquesne Light Company (DLC) j for the BVPS-1 reactor vessel on August 2,1996, the NRC staff noted that i
several parts of the analysis had been reevaluated.
In order to fully l
understand the effect of these reevaluations, the NRC staff also examined:
I 1.
DLC's response to Generic Letter (GL) 92-01 dated July 8, 1992 (J.D.
Sieber (DLC) to the U.S. Nuclear Regulatory Commission Document Control i
Desk) i 2.
A DLC submittal on the BVPS-1 reactor vessel surveillance program dated July 21,1977 (C.N. Dunn to the United States Nuclear Regulatory 4
l Commission) i i
Licensees are required by 10 CFR 50.61 to evaluate pressurized water reactor i
vessels for susceptibility to pressurized thermal shock and to establish the unirradiated reference temperature RT according to the procedures in Paragraph NB-2331 of the ASME Code. Mditionally,10 CFR 50.61 requires that a standard deviation (a on the unirradiated reference temperature be l
determined " based upon f.)he precision of the test method."
1 l
DLC's submittal in response to GL 92-01 (reference #1 above) indicated that l
results from Charpy testing of Plate B6903-1 in the materials certification l
test program were provided in Table 5 of that submittal. Additional.Charpy i
testing of unirradiated Plate B6903-1 material was conducted in conjunction l
with the vessel's surveillance program and the results of these tests were i
submitted (along with the data from Table 5) in Table 10 of the response.
Since additional data regarding the unirradiated material properties of Plate B6903-1 has been obtained subsequent to the materials certification program:
i (1)
Explain which data was used to determine RT for Plate B6903-1 and which data was used to evaluate the unirradIaTd Charpy reference curve
}
for the Plate B6903-1 surveillance material.
If all of the data submitted in Table 10 of reference #1 are believed to be valid tests for I
determining the material properties of Plate B6903-1, provide a technical justification for the exclusion of certain data points if all of the data was not used in either of these evaluations.
i (2)
If any of this data was excluded in the determination of the Plate j
B6903-1 RTenu):
Enclosure j
---r
.c--
. =..
le t
i
=
(a) Explain how DLC's analysis meets the requirement of ASME Code i
paragraph NB-2331(a)(4) which states that the reference temperature may be determined "...from a full C, ts performed." impact curve developed f minimum data points of all the C, tes (b) Evaluate what impact the inclusion of the additional data would have on DLC's determination of RT or a.
j ercus n
l (3)
Assess what impact any changes in RT or a from DLC's response to i
m i
question (2b.) would have on DLC's eval $ ation of the RT,,, vahe &
l Plate B6903-1.
(4)
Submit for NRC staff review WCAP-14554, " Beaver Valley Unit 1 Fluence Reevaluation," dated June 1996 and referenced as the basis for the fluence values used in the BVPS-1 PTS assessment. The NRC staff must review the fluence results to assess DLC's determination of the vessel's end-of-license fluence values and the fluence value? associated with the vessel's surveillance capsules.
.