ML19340C216

Application to Amend Licenses DPR-53 & DPP-69,changing Tech Specs Re Emergency Power Supply Requirements,Value Position Indication,Instrumentation for Adequate Core Cooling & Containment Isolation.W/O Proposed Tech Specs

ML19340C216
Person / Time
Site:	Calvert Cliffs
Issue date:	11/10/1980
From:	Lundvall A BALTIMORE GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8011140201
Download: ML19340C216 (3)

Text

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,;,a w .i'lc.BAl % ORE GAS AND ELECTRIC COMPANY P. O . B O X 1475

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D A LTI M O R E. M ARYLAN D 21203 g gg] b~*

Q~g h November 10, 1980 l

AntHun E.LUNDVALL,Ja.

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sume :l..y Mr. Harold R. Denton Office of Nuclear Reactor Regulation

, U. S. Nuclear Regulatory Commission Washington, D. C. 20555  !

Subject:

Calvert Cliffs Nuclear Power Plant Units Nos. 1 & 2, Dockets Nos. 50-317 & 50-318

'NI-2 Iescons Learned Category "A" Items

Reference:

URC letter dated 7/2/80 from D. G. Eisenhut  :

i to All Pressurized Water Reactor Licensees j

Dear Mr. Denton:

Baltimore Gas and Electric Company hereby requests amendments to its Operating Licenses DPR-53 and DPR-69 for Calvert Cliffs Units 1 and 2, respectively with the submittal of the enclosed proposed Technical Specifi-cations. These pt 9 posed Technical Specifications are submitted in accordance with the guidance contained in the above referenced letter and they apply to the following areas:

1) Emergency Power Supply Requirements

2) Valve Position Indication

3) Instrumentation for Inadequate Core Cooling

1) Containment Isolation 4

{ 5) Auxiliary Feedvater

6) Shift Technical Advisor Enclosure (1) provides a brief description of the changes, which are shown on the attached marked-up pages.

These proposed changes have been reviewed by our Plant Operations

! and Safety Review Committee and Offsite Safety and Review Committee, and they have concluded that the changes vill not result in an undue risk to the public health and safety.

We have determined this submittal to be fee-exempt based on the provisions contained in the referenced letter.

BALTIMORE GAS AND ELECTRIC COMPANY

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By: ,

A. E. Lundvpl, Jr.

9 /wh~/t r t-Vice Presidbnt, Supply

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s om egm

Mr. H. R. Denton Page 2 November 7, 1980 STATE OF MARYLAND:

TO WIT:

CITY OF BALTIMORE:

Arthur E. Lundvall, Jr. being duly sworn stated that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he executed the foregoing Amendment for the purposes therein set forth; that the statements made in said Amendment are true and correct to the best of his knowledge, information and belief; and that he was authorized to execute the Amendment on behalf of said corporation.

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WITN?T>S lty Hand and Notarial Seal: . L /f[1 ),, k i/AAJ s

fty Commission expires: NA ,/_ / // / A );

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cc: J. A. Biddison, Esquire G. F. Trowbridge, Esquire Messrs. E. L. Conner, Jr. - NRC R. E. Architzel - NRC

. . , rncIccure (1) f40TES REGARDIf4G TECHtllCAL SPECIFICATI0ti SUBMITTED IN RESPONSE TO ftRC LEl'iER 0F JULY 2,1980; Till-2 LESS0 tis LEARNED CKiElKiRPT7TDtS The information contained in the following notes should be included in our letter of transmittal to the fiRC.

1. Emergency Power Supply Requirements The enclosed specifications for pressurizer heaters and pressurizer relief and block valves include provisions for the operability and testing of emergency power supplies. Since the pressurizer level instruments are powered f;om a vital instrument bus, their power sources are assured by the existing Technical Specifications covering electrical distribution.

It should be noted that the suggested " functional test" for PORT s in the model specifications (see proposed LL/STS PWR 4.4.3.1.a) was deleted since the initiating channel is part of the Reactor Protective System and is tested under that specification.

2. Valve Position Indication Tables 3.3-10 and 4.3-10 have been modified to re' lect this requirement.

3. Instrumentation for Inadequate Core Cooling ,

Tables 3.3-10 and 4.3-10, as modified, include this instrumentation.

4. Containment Isolation l t

The present version of Technical Specification 3.6.4.1, including Table 3.6-1 is adequate.

5. Auxiliary Feedwater Presently, a control grade system is installed to provide " auto-start" for the Auxiliary Feedwater Pumps. The features of this installation are described in references (4) and (5). The installation of the safety grade auto-start system will be completed during the Unit 1 and Unit 2 outages starting in October, 1980, and January, 1981, respectively. Once these installations are completed, a request for a Technical Specification revision to reflect the "as installed" configuration will be requested.

6. Shift Technical Advisor The " Shift Technical Adv program as instituted at Calvert Cliffs is described by references t 1), (2), and (3). This praoram dces not require bachelor's degree or equivalen'. in ' scientific or engineering discipline. Therefore, this portion has been deleted from the model technical specification 6.3.1.

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