ML20155C163

From kanterella
Jump to navigation Jump to search

Forwards Safety Evaluation Re Alternative to Augmented Exam of Reactor Pressure Vessel Longitudinal Welds
ML20155C163
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 10/22/1998
From: Capra R
NRC (Affiliation Not Assigned)
To: Geoffrey Edwards
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Shared Package
ML20155C166 List:
References
TAC-MA1740, NUDOCS 9811020097
Download: ML20155C163 (4)


Text

. _ _ _ _ _. _ _..

~~

ock$Y l

'L ffff l

p UNITED STMES t

r j

NUCLEAR REGULATORY COMMISSION J

WASHINGTON, D.c. 300eH001 l

% Q,,

  • October 22, 1998 1

Mr. Garrett D. Edwards l

Director Licensing, MC 62A-1 PECO Energy Company Nuclear Group Headquarters l

Correspondence Control Desk P.O. Box No.195 Wayne, PA 19087-0195 i

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION (PBAPS), UNIT 2, PROPOSED ALTERNATIVE PLAN FOR EXAMINATION OF REACTOR PRESSURE VESSEL SHELL LONGITUDINAL WELDS (TAC NO. MA1740)

Dear Mr. Edwards:

By letter dated April 2,1998, as supplemented by letter dated August 12,1998, PECO Energy Company (the licensee) requested the Nuclear Regulatory Commission (NRC) staff's review and l

approval of an altemate plan for examination of the PBAPS, Unit 2, reactor pressure vessel (RPV) shell welds.

l The proposed altemative is requested for the examination of the RPV circumferential shell welds (Section XI Exam Cat. B A, item No. B1.11) as required by 10 CFR 50.55a(g)(6)(ii)(A)(2), and the inservice inspection requirements for circumferential welds in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI,1980 Edition through Winter 1981 Addenda (Table IWB-2500-1, Examination Category B-A, item No. B1.11) for two (2) operating cycles.

Additionally, the licensee stated that it is unable to meet the 90% volume coverage requirement for examination of each longitudinal weld of the PBAPS, Unit 2, RPV as required by 10 CFR 50.55a(g)(6)(ii)(A)(2). Therefore, the licensee proposes that an attemative examination plan be accepted in lieu of the 90% volume coverage.

The NRC staff has completed the evaluation of the proposed attemative plan forlongitudinal weld examinations. The review of the altemative plan for the examination of circumferential welds is in progress and will be addressed in a separate action.

l Pursuant to 10 CFR 50.55a(g)(6)(ii)(A)(5), the staff evaluated the licensee's proposed alternative l

of examining RPV shelllongitudinal welds specified in Item B1.12 of Examination Category B-A, pl

' Pressure Retaining Welds in Reactor Vessel,"in Table IWB-2500-1 of Subsection IWB of the 1989 Edition of the ASME Code,Section XI and the augmented examination requirements in 10 CFR 50.55a(g)(6)(ii)(A)(2). The NRC staff has determined that, the licensee is unable to completely comply with the requirements, and the licensee's proposed altemative provides 3

f 1

b

] [.;

u mcwem 9811020097 981022 W

PDR ADOCK 05000277 P

PDR

E G. Edwards reasonable assurance of structuralintegrity and assures that the proposed alternative would provide an acceptable level of quality and safety. Accordingly, the licensee's proposed alternative is authorized pursuant to 10 CFR 50.55a(g)(6)(ii)(A)(5).

The NRC staff's safety evaluation is enclosed.

Sincerely,

/s/

Ro' bert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-277

Enclosure:

Safety Evalatuion cc w/ encl: See next page DISTRIBUTION Docket File THarris(E-mail SE)

PUBLIC GHill(4)

PDI-2 Reading BMcCabe JZwolinski ESullivan RCapra HConrad MThadani MO'Brien OGC ACRS l

CAnderson, RGN-l Ar

,c,C, M

Rdhidifrh ~EMCB/BC OGC PDI-2/D OFFICE P

NAME Nadani:rb hhh ESullivanfh

)

RCapra 9*

DATE

/8 /$/98 h /k/98 10 /7 /98

/0//f/98 to /21/98 OFFICIAL RECORD COPY V

DOCUMENT NAME: PB1740. GEN

l G. Edwards 2-l reasonable assurance of structuralintegrity and assures that the proposed alternative would provide an acceptable level of quality and safety. Accordingly, the licensee's proposed alternative is authorized pursuant to 10 CFR 50.55a(g)(6)(ii)(A)(5).

l The NRC staff's safety evaluation is enclosed.

Sincerely, 3 M O_. bW Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-277

Enclosure:

Safety Evalatulon cc w/ encl: See next page I

l i

i l

l I

i i

4 Mr. Garrett D. Edwards Peach Bottom Atomic Power Station, PECO Energy Company Units 2 and 3 cc:

l J. W. Durham, Sr., Esquire Chief-Division of Nuclear Safety Sr. V.P. & General Counsel PA Dept. of PECO Energy Company Environmental Resources l

2301 Market Street, S26-1 P.O. Box 8469 i

Philadelphia, PA 19101 Harrisburg, PA 17105-8469 t

PECO Energy Company ATTN: Mr. J. Doering, Vice President Board of Supervisors Peach Bottom Atomic Power Station Peach Bottom Township 1848 Lay Road R.D.#1 Delta, PA 17314 Delta, PA 17314 PECO Energy Company Public Service Commission of Maryland ATTN: Regulatory Engineer, A4 SS 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 Peach Bottom Atomic Power Station Review Division P.O. Box 399 Department of Natural Resources Deha, PA 17314 B-3, Tawes State Office Building Annapolis, MD 21401 Regional 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. Kirby, Ill Company Extemal Operations - Nuclear P.O. Box 236 De!' arva Power & Light Company Hancocks Bridge, NJ 08038-0236 m

P.O. Box 231 Wilmington, DE 19899 Manager Peach Bottom Licensing PECO Energy Company l

PECO Energy Company Nuclear Group Headquarters l

Plant Manager Correspondence Control Desk Peach Bottom Atomic Power Station P.O. Box No.195 l

1848 Lay Road Wayne, PA 19087-0195 Delta, PA 17314 i