ML20214A296

Suppls 860731 Application for Amend to Licenses DPR-53 & DPR-69 Changing Tech Specs Re Moderator Temp Coefficient Limits

ML20214A296
Person / Time
Site:	Calvert Cliffs
Issue date:	11/04/1986
From:	Tiernan J BALTIMORE GAS & ELECTRIC CO.
To:	Thadani A Office of Nuclear Reactor Regulation
References
NUDOCS 8611190377
Download: ML20214A296 (17)

Text

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B A LTIMORE GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 JoscpN A.TIERNAN VicE PntsIDENT NUCLEAR ENERGY November 4,1986 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 ATTENTION:

Mr. Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Supplement (1) to Request for Amendment dated July 31,1986 Technical Specification Change to Units I and 2 Moderator Temperature Coefficient Limits (BG&E FCR 86-3003)

REFERENCES:

(A)

3. A. Tiernan (BG&E), to Ashok C. Thadani (NRC), letter dated July 31, 1986, Calvert Cliffs Nuclear Power Plant, Un't Nos.1 & 2; Docket Nos. 50-317 and 50-318, Request for Amendment (B)

Calvert Cliffs Nuclear Power Plant Final Safety Analysis Report, Unit Nos.1 & 2, Chapter 14 (C)

D. H. Jaffe (NRC), to 3. A. Tiernan (BG&E), letter dated June 17,1986, Amendment Nos.118 & 100 to Operating License Nos. DPR-53 & DPR-69, with related Safety Evaluation Report (D)

G. W. Knighton (NRC), to Messrs. K.P. Baskin (SCE) and 3.C. Holcombe (SDG& E), letter dated May 16, 1986, Issuance of Amendment No. 47 to Facility Operating License NPF-10 and Amendment No. 36 to Faci!!ty Operating License NPF-15, San Onofre Nuclear Generating Station, Unit Nos. 2 and 3 (E)

U.S. NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, NUREG-0800, Chapter 15 Gentlemen:

The Baltimore Gas & Electric Company submits this Supplement (1) to the Request for Amendment dated July 31, 1986, Reference (A). This is submitted in response to concerns raised by Mr. Scott McNeil (NRC) with Mr. Joseph Mihalcik (BG&E) via teleconference on October 27,1986, oo 8611190377 861104 PDR ADOCK 05000317 40 P

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Mr. A. C. Thadani November 4,1986 Page 2 Concern No.1 - Identification of the Feedline Break Event as not a Design Basis Event Change No. 6 of Reference (A) requests a change to Units 1 & 2 Moderator Temperature Coefficient (MTC) limits. In support of this request, a reanalysis of the Feedline Break (FLB) transient was performed due to an increased positive MTC limit. Reference (A) identifies the FLB as a non-design basis event (DBE) for Calvert Cliffs. The classification of FLB as a DBE is currently confused by conflicting use of the DBE labelin past correspondence with the NRC.

When this event was evaluated to support the installation of a safety grade Auxiliary Feedwater Actuation System (AFAS), the FSAR (Reference (B)) included the FLB event as having fallen within the scope of DBEs. At that point,1982, the FLB event was evaluated to ensure acceptability in light of the anticipated modifications to the Auxiliary Feedwater (AFW) system. In order to document the results of the FLB cvent it was placed in Chapter 14 of the FSAR during Revision

2. Since that time, the FLB event has been referred to as a DBE and as not a DBE by both BG&E and the NRC. Reference (C), the NRC Safety Evaluation Report in support of a Unit 1 AFW request for amendment, specifically refers to the FLB event as not a DBE.

BG&E acknowledges that some confusion exists as to the classification of the FLB event as a DBE. In an effort to facilitate review of Reference (A) in a timely manner, BG&E agrees to remove the sentence in Reference (A) identifying the FLB as not a DBE. The resolution of whether or not FLB is a DBE shall be dealt with via subsequent response to the NRC. Specifically, this sentence is the first sentence in the third paragraph of the Discussion section of Change No. 6, Reference (A), (i.e., "The FLB is not a Design Basis Event for Calvert Cliffs plants.").

Concern No. 2 - Classification of the Feedline Break Event with Loss of AC Power as a Very Low Probability Event The NRC staff considers the FLB event with a Loss of AC Power as a very low probability event (Reference (D)).

The Standard Revlew Plan (SRP)

(Reference (E), Chapter 15.2.8-3) states that for a low probability event, RCS pressure should be maintained below 110% (2750 psi) of the design pressure and for a ver low probability event, RCS pressure should be maintained below 120 % (3000 ps o the design pressure. For the analysis of FLB with a Loss of AC Power as presented in Reference (A), peak pressure remains well below the 120% (3000 psi) design pressure limit at a pressure of 2760 psi.

The original FLB cvent analysis, first performed in 1982 (prior to the NRC interpretation of Reference (D)) resulted in a peak Reactor Coolant System (RCS) pressure less than 110 % (2750 psi) of design pressure. Consideration of whether FLB is a low probability event or a very low probability event was not pursued at that time since the peak RCS pressure reached was less than the lowest RCS pressure (110%,2750 psi) allowed by the SRP.

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Mr. A. C. Thadani November 4,1986 Page 3 The original analysis as well as the current FLB with Loss of AC Power analysis both exhibit peak RCS pressures well below the 120 % (3000 psi) design pressure limit in the SRP for a very low probability event. In fact, the current FLB analysis for the more p(ositive MTC case only exceeds the original FLB analysis peak pressure by 11 psi i.e.,2760 psi vice 2749 psi).

Therefore BG&E affirms its position of no significant hazards determination so stated in Reference (A) since the current FLB analysis does not significantly increase the probability or consequences of an accident previously analyzed, create the possibility of a new or different type of accident from any accident previously analyzed or involve a significant reduction in margin of safety.

Concern No. 3 - Feedline Break Event Figures Figures 1-13, which graphically illustrate the results of the FLB event for the more positive MTC, are issued by this supplement and are so attached.

Very truly yours, r-N STATE OF MARYLAND :

TO WIT:

CTTY OF BALTIMORE :

Joseph A. Tiernan, being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, information, and belief; and that he was authorized to provide the response on behalf of said Corporation.

WITNESS my Hand and Notarial Seal:

,7;/-M d-m Notary Public My Commission Expires: Odpb/N h /3 /9P6 v

Date' JAT/DSE/Imt Attachments

Mr. A. C. Thadani November 4,1986 Page 4 cc:

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