ML17158C227

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Forwards SE Accepting Licensee 960506 & 0423 Submittals Re Revs to IST Programs for Plant,Units 1 & 2,respectively. Requests That Necessary Action Re Relief Requests RR-15 & 24 Be Taken & Response Provided within 120 Days from SE Date
ML17158C227
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 07/17/1997
From: Stolz J
NRC (Affiliation Not Assigned)
To: Byram R
PENNSYLVANIA POWER & LIGHT CO.
Shared Package
ML17158C228 List:
References
TAC-M95511, TAC-M95512, NUDOCS 9707230098
Download: ML17158C227 (5)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 17, 1997 Hr. Robert G.

Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101

SUBJECT:

SAFETY EVALUATION FOR SUSQUEHANNA STEAM ELECTRIC STATION (SSES),

UNITS 1

AND 2, INSERVICE TESTING RELIEF REQUESTS (TAC NOS.

H95511 AND H95512)

Dear Hr. Byr am:

By letters dated Hay 6,

1996, and April 23,
1996, Pennsylvania Power and Light Company (PPKL) submitted revisions to the inservice testing programs for SSES, Units 1 and 2, respectively.

The revised programs include changes made in response to NRC's safety evaluation (SE), for the second 120-month interval for both units, dated April 26, 1995.

In a letter dated August 4,

1995, PPEL responded to certain items related to relief requests that were denied in the NRC's safety evaluation.

The revised programs include the changes made related to the August 1995 response.

Several relief requests have been revised and are evaluated in the enclosed SE.

You also submitted a letter dated Hay 20, 1996, that included revised Relief Request RR-23 for both units, which is evaluated in the enclosed SE.

For Relief Request RR-3, which is approved pursuant to 10 CFR 50.55a(f)(6)(i),

the NRC has determined that relief may be granted and is imposing the proposed alternative as discussed in the evaluation and conclusion.

The granting of such relief is authorized by law, giving due consideration to the burden upon the licensee that could result if the Code requirements were imposed on the facility.

Relief Request RR-23 is authorized pursuant to 10 CFR 50.55a(a)(3)(ii) in that compliance with the specified Code requirements would result in hardship nr unusual difficulty without a compensating increase in the level of quality and safety.

New Relief Requests RR-25, RR-26, RR-27, RR-28, RR-29, RR-30, ano RR-31 have been developed in accordance with the guidance in Position 2 of Generic Letter (GL) 89-04 for disassembly and inspection of applicable check valves and are therefore acceptable alter natives.

RR-32 is considered acceptable under provisions in OH-10 and,.

therefore, relief is not required;

however, the request is effectively a cold shutdown/refueling outage justification.
Overall, PPEL's actions generally addressed the recommendations in the April 1995 NRC SE;
however, upon review of the enclosed SE, you must take further a tions for Reli'ef Request RR-15 as discussed in Section 3.4 of the SE and 9707230098 970717 PDR ADQCK 05000387 P

PDR llllllllllllllllllllllllllllllilllllllll F28 PilK KHlER CIEPV

R.

Byram Relief Request 24 as discussed in Section 3. 14 of the SE.

Please take the necessary actions and provide a response within 120-days from the date of this SE.

Depending on the course of action taken by the licensee, NRC review and evaluation of revised relief requests may be necessary.

Sincerely, Docket Nos. 50-387/388

Enclosure:

Safety Evaluation cc w/encl:

See next page J

h

. Stolz, Direc ject Directorate

-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

R.

Byram July 17, 1997 Relief Request 24 as.discussed in Section 3. 14 of the SE.

Please take the necessary actions and provide a response within 120-days from the date of this SE.

Depending on the course of action taken by the licensee, NRC review and evaluation of revised relief requests may be necessary.

C Sincerely,

/s/

Docket Nos.

50-387/388

Enclosure:

Safety Evaluation cc w/encl:

See next page DISTRIBUTION John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket File PUBLIC PDI-2 Reading SVarga JStolz CPoslusny MO'Brien THarris (E-Mail SE)

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0 Mr. Robert G.

Byram Pennsylvania Power

& Light Company l

CC Susquehanna Steam Electric Station, Units 1

& 2 Jay Silberg, Esq.

Shaw, Pittman, Potts

& Trowbridge 2300 N Street N.W.

Washington, D.C.

20037 Bryan A. Snapp, Esq.

Assistant Corporate Counsel Pennsylvania Power

&, Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.

H. Kenny Licensing Group Supervisor Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. K. Jenison Senior Resident Inspector U.

S. Nuclear Regulatory Commission P.O.

Box 35 B rwick, Pennsylvania 18603-0035 Hr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P.

O.

Box 8469 Harrisburg, Pennsylvania 17105-8469 Hr. Jesse C. Tilton, III

.Allegheny Elec. Cooperative, Inc.

212 Locust Street P.O.

Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hr. George Kuczynski Plant Hanager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Hr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,

Box 1797 Berwick, Pennsylvania 18603 George T. Jones Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA.

16803 Chairman Board of Supervisors 738 East Third Street

Berwick, PA 18603