ML20070C381

TS Change Request 90-05 to Licenses DPR-277 & DPR-44, Implementing Fire Protection,Per GL 86-10 & Removing Fire Protection Requirements from Ts,Per GL 88-12

ML20070C381
Person / Time
Site:	Peach Bottom
Issue date:	06/27/1994
From:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20070C385	List: ML20070C381
References
GL-86-10, GL-88-12, NUDOCS 9407050242
Download: ML20070C381 (4)

Text

e , Station Support Department 10 CFR 50.90 E3fk PECO ENERGY  ;=gg;;;L U$,$ $ $35 "

June 27,1994 Docket Nos. 50 277 50 278 Ucense Nos. DPR 44 DPR 56 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Peach Bottom Atomic Power Station, Units 2 and 3 Technical Specification Change Request

Reference:

Letter from G. A. Hunger, Jr. (PECO) to NRC dated March 28,1994

Dear Sir:

In the above referenced letter, PECO Energy Company (PECO Energy) submitted, in accordance with 10 CFR 50.90, Technical Specification Change Request (TSCR) 90 05, which requested changes to Appendix A of the Peach Bottom Atomic Power Station (PBAPS) Operating Licenses. The proposed changes concerned the relocation of the Technical Specifications Fire Protection requirements to the Updated Final Safety Analysis Report in accordance with NRC Generic Letter (GL) 8610, " Implementation of Fire Protection Requirements," and GL 8812 " Removal of Fire Protection Requirements from Technical Specifications."

PECO Energy hereby requests that our original submittal be revised such that the submitted Units 2 and 3 pages 244,246 and 252 be deleted and replaced with the attached revised Units 2 and 3 pages 244,246 and 252. Revisions to -

these pages were necessary to incorporate recently approved amendments, and to revise the audit frequency of the Fire Protection Program by the Nuclear Review Board. This issue was discussed between Ken Graff (PECO Energy)  !

and Steve Dembek (NRC) on June 17,1994.

1 1)ssF

.94o705o242 940627 00

[d81)

PDR ADOCK 05000277 P PDR

Juno 27,1994 Page 2 We have determined that this revision does not alter our evaluation of any of the 10 CFR 50.59 standards, and therefore, does not affect our conclusion that TSCR 9045 does not constitute an unreviewed safety question. Also, we have concluded that the proposed revision does not affect the information supporting a finding of No Significant Hazards Consideration and the information supporting an EnvironmentalImpact Assessment.

If you have any questions concerning this submittal, please contact us.

Sincerely,

. W , .

G. A. Hunger,[Jr.

Director - Licensing

Enclosures:

Affidavit, Attachment I

cc: T. T. Martin, Administrator, Region I, USNRC

, W. L. Schmidt, Senior Resident Inspector, PBAPS, USNRC i R. R. Janati, Commonwealth of Pennsylvania i

i

l COMMONWEALTH OF PENNSYLVANIA :

ss.

COUNT ( OF CHESTER  :

W. H. Smith, lil, being first duly sworn, deposes and says:

That he is Vice President of PECO Energy Company; the applicant herein; that he has read the attached revised Technical Specification Change Request (TSCR 90-

05) for changes to the Peach Bottom Facility Operating Licenses DPR-44 and DPR-56, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

[.-

Vice Pre,sident Subscribed and sworn to before me this J day of h Q 1994.

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t Unit 2 PBAPS Continued 6.2.2 Facility Staff The facility organization shall be subject to the following:

a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.1, except that the shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

b. At least one licensed operator shall be in the control room and assigned to each reactor that contains fuel,

c. At least two licensed operators, excluding the operator on the second unit, shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.

d. An individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor.

e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-

. sibility during this operation.

f. Deleted.

g. In addition to the requirements of 6.2.2.a, the Senior Manager-

+-

Operations shall hold a Senior Reactor Operator license.

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