ML20003E145

Application for Amend to License DPR-56,revising Tech Specs to Accommodate Fourth Refueling of Reactor & Identifying Operating Limits for All Fuel Types for Cycle 5 Operation. Certificate of Svc Encl

ML20003E145
Person / Time
Site:	Peach Bottom
Issue date:	03/27/1981
From:	Bauer E, Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20003E138	List: ML20003E137 ML20003E145 ML20003E147 ML20003E148 ML20003E150 ML20003E154 ML20003E155
References
NUDOCS 8104020325
Download: ML20003E145 (9)

Text

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BEFORE THE l

UNITED STATES NUCLEAR REGULATORY COMMISSION l

In the Matter of  :

,  : Docket No. 50-278 PHILADELPHIA ELECTRIC COMPANY  :

APPLICATION FOR AMENDMENT OF FACILITY OPERATING LICENSE DPR-56 l

Edward G. Bauer, Jr.

Eugene J. Bradley i

2301 Market Street

! Philadelphia, Pennsylvania 19101 Attorneys for Philadelphia Electric Company l'

F CG04020SAS.

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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSI'.1.

In the Matter of  :

Docket No. 50-278 PHILADELPHIA ELECTRIC COMPANY  :

APPLICATION FOR AMENDMENT OF FACILITY OPERATING LICENSE DPR-56 Philadelphia Electric. Company, Licensee under ascility Operating License DPR-56 for Peach Bottom Unit 3, hereby requests that the Technical Specifications contained in Appendix A of the Operating License be amended-by revising certain sections as indicated tar a vertical bar in the margin of attached pages iv, vi, 4, 9, 10, 11, 13, 14, 17, 19, 20, 21, 24, 31, 33, 40, 74, 91, 92, 103, 104, 111, 133a, 133b, 133c, i33d,-140,.140a, 140b, 140c, 140d,_142f, 142g, 152a, 157, and 241. .The information on pages 140e,.142, and 142a has been deleted. Page numbers 142 and 142a, however, have been re-issued with new information. Page numbers

.133e, 142h, and 1421 are new pages. r

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• The changes to the Technical Specifications are boing requested to: (1) accommodate the fourth refueling of the Peach Bottom Unit 3 reactor, (2) identify the operating limits for all fuel types for cycle 5 operation, (3) permit the continued use of the fast scram control rod drive during cycle 5, (4) permit continued operation of the Pressurized Test Assembly (PTA) after re-constitution with six (6) new fuel rods, (5) incorporate the 67B control rod drive scram times, (6) accommodate implementation of ODYN transient analysis code into reload licensing, (7) delete certain Technical Specification Bases LOCA information which is redundant to information contained in other previously submitted documents, (8) incorporate MAPLHGR limits for the Reload 4 fuel and extended exposure MAPLHGR limits for the Reload 2 and Reload 3 fuel, (9) add generic MAPLHGR curve for P8x8R fuel to reduce need for future cycle-dependent revisions, and (10) modify references given in the Bases regarding reload safety evaluations.

An analysis of the safety considerations invclved in the reactor refueling and the cycle 5 operating limits for all fuel types is set forth in a document entitled " Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station Unit 3 Reload 4"'(Y1003J01A20) February, 1981, which is filcd herewith and incorporated herein by reference.

An analysis of the safety considerations involved in continuing the use of the fast scram control rod drive (FSCRD) during cycle 5 is set forth in a document enti. led " General Electric Boiling' Water Reactor Reload 1 Licensing Amendment for Peach Bottom Atomic Power Station Unit No. 3, Fast Scram Control i

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- Rod Drive Third Supplement" (NEDO-21363-3) February, 1981, which is filed herewith and incorporated herein by reference.

In addition, the changes requested herein would permit the continued operation of the Pressurized Test Assembly (PTA) which was initially inserted into the Peach Bottom 3 reactor during the Spring, 1977, Reload 1 refueling. This PTA will be inspected and re-configured during the Peach Bottom 3 Reload 4

, refueling outage. A total of six (6) irradiated fuel rods will i

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txt removed and replaced with new fuel tods prior to bundle re-insertion for Cycle 5 operation. The. purpose of continued PTA operation is to obtain fission gas measurements trom the PTA in conjunction with the fuel extended exposure program.. The

, estimated PTA bundle average exposure at the Spring, 198.1, refueling outage is approximately 26 GWD/MT. An additional cycle

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of operation will extend the fuel bundle average exposure to approximately 34 GWD/MT, with a peak pellet exposure approaching 44 GWD/MT. An analysis of the safety considerations involved in continuing the use of the PTA is set forth in appendix F of document Y1003J01A20.

The amendment request proposes that the 67B control rod drive (CRD) scram times be incorporated into the Technical Specifications. The 67B'CRD scram times, in replacing the 67A scram times, require a 3.5 second average scram insertion time, rather'than 5.0 second average scram insertion time (67A), for the.90% inserted from the fully _ withdrawn position._ This change is1 proposed 1to be in conformance with the reload-unique transieut analysis: inputs utilized:in the aforementioned document Y1003J01A20. ,

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The amendment request changes provide for the implementation of the ODYN transient analysis code for analysis of rapid pressurization and over-pressure protection events as set forth in the " Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station Unit 3 Reload 4" (Y1003J01A20).

The MCPR's calculated for the pressurization events analyzed with ODYN have been adjusted in accordance with Option B of the ODYN implementation plan. In the event that the Option B scram time l specification is not mei. , linear interpolation between the Option A MCPR and the Option B MCPR will be performed. Both the Option A and Option B cycle MCPR values and implementation procedure including ODYN Option B MCPR Scram Insertion Time Conformance Procedure are incorporated herein as described in the letter dated September 5, 1980, R.H. Buchholz (General Electric) to P. S. Check (U.S. NRC), " Response to NRC Request for Information on ODYN Computer Model."

The proposed changes requested on pages 13, 14, 140a, and deletion of page 140e would delete certain portions of the j Bases of the Technical Specifications that contain information which is redundant to information contained in General Electric l documents NEDE-24011-P-A, " General Electric Boiling Water Reactor Generic Reload Fuel Application" and NEDO 24082, " Loss-of-Coolant l Accident Analysis for Peach Bottom Atomic Power Station Unit 3."

l The proposed changes to the Bases eliminate the necessity of l revising these sections of the-Technical Specifications for each reload.

The proposed changes incorporate MAPLHGR limits for the

! Reload 4 fuel and' extended exposure'MAPLHGR limits for the Reload r

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r 2 and Reload 3 fuel. An analysis of the safety considerations involved in these MAPLHGR limits is set forth in a document entitled " Loss of Coolant Accident ..'ealysis for Peach Bottom Atomic Power Station Unit 3," Errata and Addenda Number 3 and 4 to NEDO-2408L, which are filed herewith and incorporated herein by reference.

The proposed generic P8x8R MAPLHGR curve addition on page 1421 is added for the purpose of reducing the need for future cycle-dependent revisions to the Technical Specifications.

This curve has been constructed to bound the Reload 3 and Reload 4 P8X8R fuel.

The changes requested herein modify references in the Bases of the Technical Specifications to the General Electric reload safety evaluation document for a specific fuel cycle, and the results of that analysis for a specific fuel cycle, in order to accommodate future refuelings in accordance with the provisions of 10 CFR Section 50.59.

Since the proposed changes to the Technical Specifications do not involve a significant hazards consideration, pursuant to 10 CFR Section 170.22, Philadelphia Electric Company for fee purposes, proposes that the Application for Amendment be considered a Class III Amendment.

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- The Plant Operation Review Committee and the Operation and Safety Review Committee have reviewed these proposed changes ,

to the Technical Specifications, and have concluded that they do not involve an unreviewed safety question or a significant hazard

consideration and will not endanger the health and safety of the 1

public, i

Respectfully submitted, s

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Vice President / l 4

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COMMONWEALTH OF PENNSYLVANIA  :

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COUNTY OF PHILADELPHIA  :

S. L. Daltroff, being first duly sworn, deposes and says:

That he is Vice President of Philadelphia Electric Company, the Applicant herein; that he has read the foregoing Application for Amendment of Facility Operating License 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.

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Subscribed and swor to before me this day of . ( C b .

o ary Publitt EU7., DETH H.COYE:1 Pkt = " ofic, Ph!!JL, Ph!!a. CO. '

(fy Commissicn Expires Jan. 30,1S32

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CERTIFICATE OF SERVICE I certify that service of the foregoing Application was made upon the Board of Supervisors, Peach Bottom Township, York County, Pennsylvania, by mailing a copy thereof, via first-class mail, to Albert R. Steele, Chairman of the Board of Supervisors, R. D. No. 1, Delta, Pennsylvania 17314; upon the Board of Supervisors, Fulton Township, Lancaster County, Pennsylvania, by

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mailing a copy thereof, via first-class mail, to George K.

Brinton, Chairman of the Board of Supervisors, Peach Bottom, Pennsylvania 17563; and upon the Board cf Supervisors, Drumore Township, Lancaster County, Pennsylvania, by mailing a copy thereof, via first-class mail, to Wilmer P. Bolton, Chairman of the Board of Supervisors, R. D. No. 1, Holtwood, Pennsylvania 17532; all this 30th day of Nbrch, 1981

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EugeneJ.Bradly A'torney for Philadelphia Electric Cor ny W

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