ML20062E702

Application to Amend Licenses DPR-53 & DPR-69,revising Tech Specs to Incorporate Listed Changes Re ASME Code Addenda, Rcs,Reg Guide 1.33 & Leak Rate Testing

ML20062E702
Person / Time
Site:	Calvert Cliffs
Issue date:	08/02/1982
From:	Lundvall A BALTIMORE GAS & ELECTRIC CO.
To:	Clark R Office of Nuclear Reactor Regulation
Shared Package
ML20062E704	List: ML20062E702 ML20062E708
References
RTR-REGGD-01.033, RTR-REGGD-1.033 NUDOCS 8208100272
Download: ML20062E702 (5)

Text

3 BALTIMORE GAS AND ELECTRIC I i

CHARLES CENTER P.O. BOX 1475

• BALTIMORE, MARYLAND 21203 ARTHUR E. LUNOVALL. JR.

vice PatslOENT Suppty August 2,1982 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docker Nos. 50-317 & 50-318 Request for Amendment Gentlemen:

Baltimore Gas and Electric Company (BG&E) hereby requests Amendments for Operating Licenses DPR-53 and DPR-69 for Calvert Cliffs Units 1 and 2, respectively with the submittal of the enclosed proposed change to the Technical Specifications.

TECHNICAL SPECIFICATION CHANGES CHANGE NO.1 (FCR 81-121)

Incorporate revised Technical Specification 4.4.10.1.2 as shown on marked up sheet 3/4 4-28.

DISCUSSION AND JUSTIFICATION The Technical Specification presently states that the rules, acceptance criteria, and repair procedures of ASME Code Section XI,1974 Edition and Addenda through Summer 1976, for Class 2 components, are to be used subject to the changes stated in the Specification. The inclusion of Addenda through Summer 1976 is believed to be a typographical error, with the intended Addenda through Summer 1975. The Summer 1976 Addenda has' not been approved by the Nuclear Regulatory Commission and was never included in 10 CFR 50.55 a(g), Inservice Inspection Requirements. A fOD !

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Mr. R. A. Clark August 2,1982 Page 2 CHANGE NO. 2 (FCR 81-99)

Incorporate revised Technical Specification 4.5.2.g.2 as shown on marked up page 3/4 5-Sa.

DISCUSSION AND JUSTIFICATION The Technical Specification presently requires checking of the Main High Pressure Safety Injection Loop isolation valve 12A and 22A (MOV-646) under the column listing the Auxiliary High Pressure Safety Injection Loop isolation valves for the other three loops.

This is believed to be a typographical error, with the actual valve requiring the test to be MOV-647, the Auxiliary High Pressure Safety Injection loop isolation valve for 12A and 22A. This is further justified by the valve being listed twice under the same action step.

CHANGE NO. 3 (FCR 81-100)

Incorporate revised Technical Specification 3.4.3.c as shown on the attached marked up page 3/4 4-4.

DISCUSSION AND JUSTIFICATION Two changes are requested in this Technical Specification. First, since the Final Safety Analysis Report requires only the Pressurizer Code Safety Valves be operable to protect the RCS from overpressurization, the inoperability of the power operated relief valves should not preclude the ability to change modes. Secondly, since the inoperability of the block valve would prevent its operation open or closed, the requirement to cycle the valve each 92 days should not be required.

CHANGE NO. 4 (FCR 82-10)

Incorporate revised Technical Specification 6.8.1.a as shown on attached marked up page 3/4 6-13.

DISCUSSION AND 3USTIFICATION As previously listed in TS 6.3.1.a, we were committted to NRC Regulatory Guide 1.33 Revision 1972. However, when the 1978 Revision of Reg. Guide 1.33 was issued, we were committed to this revision. Therefore, we are requesting addition of revision to the Reg.

Guide tre which we are committed. Section IC of the Final Safety Analysis Report and Sectis IC of the Calvert Cliffs Quality Assurance Manual also list the current revision ut Regulatory Guides to which BG &E is committed.

Mr. Robert A. Clark August 2,1982 Page 3 CHANGE NO. 5 (FCR 82-38)

Incorporate revised Technical Specification Table 3.7-4, page 3/4 7-60 as shown on revised, marked up page 3/4 7-60.

DISCUSSION AND JUSTIFICATION The Table currently lists Main Steam Line Encapsulation 27' Snubber 1-38-49. The Startup System Number for Main Steam in Number 83, so this number should actually be 1-83-49. The redundant snubber in Unit 2 Technical Specification is listed correctly.

This error is believed to have been the result of a typographical error.

CHANGE NO. 6 (FCR 82-122)

Incorporate revised Technical Specifications 3.6.1.2, 3.6.1.3, 4.6.1.2, 4.6.1.3, and 4.6.4.1 as shown on attached marked-up pages 3/4 6-2, 3/4 6-3, 3/4 6-4, and 3/4 6-8 for Unit Nos. I and 2.

DISCUSSION AND JUSTIFICATION The Technical Specifications presently list the limits for local and integrated leak rate testing as a fraction of L aand L values.

t Translation of these values into surveillance procedures requires a calculation converting % by weight of air per day (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) as listed in the Technical Specification to standard cubic centimeters per minute (sccm).

The only variable in this calculation is containment gir free volume. Since the total air i free volume of the containment is listed as 2 x 10 cubic feet (from the Final Safety l Analysis Report (FSAR) Section 5) a major volume change would be required to significantly affect this value. This concept has been verified by calculations made by the Architectural Engineer which supplied the design and construction of the containment. The Architectural Engineer also verified that the free volume figure is accurate to three to four significant figures. To ensure conservatism in the limit values used in the Technical Specifications, the values are expressed in three to four significant figures, rounded to the more conservative direction. This change represents an administrative clarification of the present Technical Specification limits and as such does not change or reduce the original design bases described in the FSAR.

Calculations of Leakage Rates for Value of 3L and L t for Unit I La (from Bechtel reports) = .2% day Pa = 50 psig (64.696 psia)

(and Tech Spec 3.6.1.3)

La= .2%

x 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> x 2 x 106 ft3 x 2.831'l x 104 cc x 64.696 psia =

24 hrs 60 mins 100 % ft' 14.696 psia 346,276.5 secm > 346,000 sccm

Mr. Robert A. Clark August 2,1982 Page 4 Lt (from Bechtel reports) = .058%/ day Pt = 25 psig (39.696 psia)

(and Tech Spec 3.6.1.3)

L=t

.058 % x 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> x 2 x 106 ft3 x 2.8317 x LO4 cc x 39.696 psia =

24 hrs 60 mins 100 % ft> 14.696 psia 61,615.6 sccm > 61,600 sccm Fractions of L 3 Fractions of L

.75 La = 259,500 sccm .75 Lt= 46,200 sccm

.60 La = 207,600 sccm .25 Lt= 15,400 sccm

.25 La = 86,500 sccm

.05 La = 17,300 sccm

.0002 La = 69.2 sccm Calculations of Leakage Rates for Value of 3L and L3 for Unit 2 (Lavalue is same for Unit Nos. I and 2)

Lt (from Bechtel reports) = .042%/ day Pt= 25 psig (39.696 psia)

(and Tech Spec 3.6.1.3) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 6 3 2.831Z x 104 cc 39.696 psia =

Lt= .042 %

24 hrs x

60 mins x 2 x 10 ft 100 %

x ft>

x 14.696 psia l 44,618 sccm > 04,600 sccm Fractions of L 3 l

.75 Lt= 33,400 sccm i

.25 Lt= 11,100 sccm i

l SAFETY COMMITTEE REVIEW I

l This proposed change to the Technical Specifications has been reviewed by our Plt.at l Operations and Safety and Off-Site Safety Review Committees, and they have concluded that implementation of this change will not result in an undue risk to the health and l safety of the public.

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Mr. Robert A. Clark August 2,1982 Page5 FEE DETERMINATION We have determined, pursuant to 10 CFR Part 170.22, that this Amendment request constitutes Class IV and I amendments for Calvert Cliffs Unit Nos. I and 2, respectively, and, accordingly, we are including BG&E Check No. B066352 in the amount of 512,700 to cover the fee for this request.

BALTIMORE GAS AND ELECTRIC COMPANY

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Vice President - Supply AEL/LES/gla STATE OF MARYLAND  :

TO WIT:

CITY OF BALTIMORE  :

Arthur E. Lundvall, 3r., 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: ido Notary Public My Commission Expires: --

)x4 /,, N f cc: 3. A Biddison, Esquire j G. F. Trowbridge, Esquire  !

D. H. Jaffe, NRC l R. E. Architzel, NRC I

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