ML20247N518
| ML20247N518 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom |
| Issue date: | 05/11/1998 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | Geoffrey Edwards PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| Shared Package | |
| ML20247N523 | List: |
| References | |
| TAC-M98850, TAC-M98851, NUDOCS 9805270170 | |
| Download: ML20247N518 (4) | |
Text
- _ - _ _
na 50 ~ 2 77 k
p UNITED STATES g
NUCLEAR REGULATORY COMMISSION a
WAsNINGTON, D.c. 30006 4001 May 11, 1998 Mr. Garrett D. Edwards Director-Licensing, MC 62A-1 PECO Energy Company Nuclear Group Headquarters Correspondence Control Desk P.O. Box No.195 Wayne, PA 19085-0195
SUBJECT:
THIRD 10-YEAR INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AN VALVES, PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 (TAC NOS. M98850 AND M98851)
Dear Mr. Edwards:
By a letter dated May 8,1997 and a later revision dated February 13,1998, PECO Energy Company (the licensee) submitted requests for relief from American Society of Mechanical i
Engineers (ASME) Code,Section XI requirements for its third 10-year interval inservice testing (IST) program for Peach Bottom Atomic Power Station, Units 2 and 3. The third 10 year interval for Units 2 and 3 began on November 5,1997, and ends on November 4,2007. The licensee's submittels were found to be of very good quality; however, two of the relief requests (GVRR-1 and GVRR-4) were not supported by descriptions of hardship or unusual difficulty in performing the Code testing and thus were denied by the NRC staff.
With technical assistance from Idaho National Engineering and Environmental Laboratory i
(INEEL), we have reviewed the information concoming the licensee's IST program and requests for relief from ASME Code. Based en the review of the information submitted, the staff adopts the evaluations and recommendations for granting relief or authorizing altamatives contained in the Technical Evaluation Report (TEh) prepared by INEEL, and as reflected or modified in the enclosed safety evaluation (SE). Relief is granted from or altomatives are authorized for the testing requirements which have been determined to be impractical to perform, where an attemative provides an acceptable level of quality and safety, or where compliance would result in a hardship or unusual difficulty without a compensating increase in quality or safety. The Nuclear Regulatory Commission's (NRC) staff response and the bases for its ections are outlined in the enclosed SE and its attachments.
The licensee is authorized in the enclosed SE to base the Peach Bottom IST program on the requirements of the ASME Operations and Maintenance (OM) Code-1990 in lieu of the 1989 Edition of ASME Section XI, Subsections IWP and IWV, which is referenced in 10 CFR 50.55s.
ASME OM Code 1990 is a reformat of the ASME OM Standard and includes Part 6 for IST of pumps (referenced by Subsection IWP), and OM Standard, Part 10, for IST of valves (referenced by Subsection IWV). The relief requests were reviewed against the requirements of ASME OM Code 1990 for pumps and valves. A summary of the NRC's action is provided in Attachment 1 to the enclosed SE. The test deferrals for valves which are in accordance with Part 10 have been reviewed and are summarized in Append' c C of the TER.
o l
. - _ - 31 SISC E52 2NIE3 WV 4
f 980527017o 980511 PDR ADOCK 05000277 P
pop
- r G. Edwards The IST program relief requests which are granted or authorized are acceptable for implementation provided the program anomalies identified in Appendix A of the TER (Attachment 2 to the enclosed SE) are addressed within one year of the date of the SE or by the end of the next refueling outage, whichever is later, unless another period is specified. The granting of relief is based upon the fulfillment of any commitments made by the licensee in the basis for each relief request and the attematives proposed. Where interim relief has been I
granted, the licensee should resolve the issues before expiration of the interim period. The licensee is requested to respond to the NRC within one year of the date of this SE describing actions taken, actions in progress, or actions to be taken, to address each of these items.
l Program changes involving new or revised relief requests should be submitted to the NRC. New or revised relief requests that meet the positions in NRC Generic Letter 89-04, Attachment 1, should be submitted to the NRC but may be implemented provided the guidance in GL 89-04, Section D, is followed.
Sincerely,
/S/
l Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects -l/II Office of Nuclear Reactor Regulation l
Docket Nos. 50-277/50-278 l
4
Enclosure:
SE 1
cc w/ encl: See next page DISTRIBUTION Docket File PUBLIC PDI-2 Reading JZwolinski' RCapra MThadani MO'Brien I
THarris (e-mail SE)
BMcCabe JCollaccino l
CAnderson, RGN-l OFFICE PDI-2/PMh[N PDF27LAk OG[M PDI-2/D NAME MThadani:
Mkrh MV5WW/
RCapra W DATE 4 /N/98 bb98
- / /98 5 Ill l98 OFFICIAL RECORD COPY
\\
l tyd' f.
DOCUMENT NAME: PB98850.REL 34
, gjjj
\\
G. Edwards.
The IST program relief req'uests which are granted or authorized are acceptable for implementation provided the program anomalies identified in Appendix A of the TER (Attachment 2 to the enclosed SE) are addressed within one year of the date of the SE or by the end of the next refueling outage, whichever is later, unless another period is specified. The granting of relief is based upon the fulfillment of any commitments made by the licensee in the basis for each relief request and the attematives proposed. Where interim relief has been granted, the licenses should resolve the issues before expiration of the interim period. The licensee is requested to respond to the NRC within one' year of the date.of this SE describing actions taken, actions in progress, or actions to be taken, to address each of these items.
Program changes involving new or revised relief requests should be submitted to the NRC. New or revised relief requests that meet the positions in NRC Generic Letter 8g-04 Attachment 1, should be submitted to the NRC but may be implemented provided the guidance in GL 8g-04, Section D, is followed.
Sincerely,.
Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation Docket Nos. 50 277/50 276
Enclosure:
SE cc w/ encl: See next page e
e Wr e
F Mr. Garrett D. Edwards PECO Energy Company Peach Bottom Atomic Power Station, Units 2 and 3 cc:
J. W. Durham, Sr., Esquire Chief Division of Nuclear Safety Sr. V.P. & General Counsel PA Dept. of PECO Energy Company Environmental Resources 2301 Market Street, S26-1 P.O. Box 6469 Philadelphia, PA 19101 Harrisburg, PA 17105-6469 PECO Energy Company
~
ATTN: Mr. T. N. Mitchell, Vice President Board of Supervisors i
Peach Bottom Atomic Power Station Peach Bottom Township 1848 Lay Road R.D.#1 Delta, PA 17314 Delta, PA 17314 PECO Energy Company ATTN: Regulatory Engineer, A4 5S Public Service Commission of Maryland i
Engineering Division Peach Bottom Atomic Power Station Chief Engineer 1848 Lay Road 6 St. Paul Centre Delta, PA 17314 Baltimore, MD 21202-6806 Resident inspector Mr. Richard McLean U.S. Nuclear Regulatory Commission Power Plant and Environmental l
Peach Bottom Atomic Power Station Review Division l
P.O. Box 399 Department of Natural Resources Delta, PA 17314 B-3, Tawes State Office Building Annapolis, MD 21401 Regiona! Administrator, Region i U.S. Nuclear Regulatory Commission Dr. Judith Johnsrud 475 Allendale Road National Energy Committee King of Prussia, PA 19406 Sierra Club 433 Orlando Avenue Mr. Roland Fletcher State College, PA 16803 Department of Environment 201 West Preston Street Manager-Financial Control & Co-Owner Baltimore, MD 21201 Affairs Public Service Electric and Gas A. F. IGrby, til Company Extemal Operations - Nuclear P.O. Box 236 Delmarva Power & Light Company Hancocks Bridge, NJ 08038-0236 P.O. Box 231 Wilmington, DE 19899 Manager Peach Bottom Licensing PECO Energy Company PECO Energy Company Nuclear Group Headquarters Plant Manager Correspondence Control Desk Peach Bottom Atomic Power Station P.O. Box No.195 1848 Lay Road Wayne, PA 19087-0195 Delta, PA 17314 i
l