ML20245H957

Affirms Position That Plant Reactor Bldg Closed Cooling Water Sys Containment Isolation Valves Must Undergo Local Leak Rate Testing Per App J to 10CFR50

ML20245H957
Person / Time
Site:	Millstone
Issue date:	08/14/1989
From:	Varga S Office of Nuclear Reactor Regulation
To:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO.
References
TAC-73760, NUDOCS 8908170372
Download: ML20245H957 (3)

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UNITED STATES A r,,.

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9 August 14,.1989 IDocket No. 50-336~

C Mr. Edward J. Mroczka

. Senior Vice President-L INuclear Engineering.and Operations Co necticutLYankee Atomic Power Company Northeast Nuclear Energy Company P.O. Box 270 Hartford,' Connecticut' 06141-0270

SUBJECT:

MILLSTONE NUCLEAR STATION, UNIT NO. 2 REACTOR BUILDING CLOSED COOLING WATER (RBCCW) SYSTEM - CONTAINMENT ISOLATION VALVES (TACNO.73760)

We have completed our_ review of your June 20; 1989 letter regarding your

'backfit concerns over the staffs position to keep leak rate testing of the Millstone Unit 2 RBCCW containment isolation valves in the Appendix J program. Table 5'.2-11 of the Millstone Unit 2 FSAR identifies the subject RBCCW valves as requiring Type "C" testing; thus, these valves have been established as containment isolation valves requring Type-"C"Ltesting as part of the current' design basis of.the facility.

In addition, as discussed in our earlier letters..it is our position that Appendix.J to 10 CFR Part 50 ~

requires these valves t.o be tested. Your letter of January 7,1988 clearly

. identifies the associated RBCCW piping and containment air recirculation

. cooling coils inside containment as being fabricated 'to Safety Class 3 standards. While we' agree that.the subject RBCCW piping provides a closed system inside containment, the existence of Safety Class 3 components in the system does.not provide adequate assurance of post-accident integrity. We are not proposing that you change the design basis of the RBCCW system inside containment; however, you have not provided acceptable justification for

' suspension of Type "C" testing for the RBCCW containment isolation valves, and therefore must continue to Type "C" test these valves in accordance with Appendix J.

Since Appendix J (Type "C") testing of the subject containment isolation valves was part of the original design basis for Millstone Unit 2, denial of L

relief from such testing cannot be considered as a "Backfit" within the definitionstatedin10CFRPart50,Section50.109(a)(1).

1 8908170372 890814 PDR ADOCK 05000336 P-PDC

9 Mr. Edward J. Mroczka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 CC:

Gerald Garfield, Esquire R. M. Kacich, Manager Day, Berry and Howard.

Generation Facilities Licensing Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Romberg, Vice President D. O. Nordquist Nuclear Operations Manager of Quality Assurance Northeast Utilities Service Company Northeast Nuclear Energy Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region I Department of Environmental Protection U. S. Nuclear Regulatory Commission State Office Building 475 Allendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Bradford S. Chase, Under Secretary First Selectmen Energy Division Town of Waterford Office of Policy and Management Hall of Records 80 Washington Street 200 Boston Post Road Hartford, Connecticut 06106 Waterford, Connecticut 06385 S. E. Scace, Station Superintendent W. J. Raymond, Resident Inspector Millstone Nuclear Power Station Millstone Nuclear Power Station Northeast Nuclear Energy Company c/o U. S. Nuclear Regulatory Commission Post Office Box 128 Post Office Box 811 4

Waterford, Connecticut 06385 Niantic, Connecticut 06357

- i J. S. Keenan, Unit Superintendent Charles Brinkman, Manager Millstone Unit No. 2 Washington Nuclear Operations Northeast Nuclear Energy Company C-E Power Systems Post Office Box 128 Combustion Engineering, Inc.

Waterford. Connecticut 06385 12300 Twinbrook Pkwy i

Suite 330 l

Rockville, Maryland 20852 4

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Mr. Edward J. Mroczka 'Accordingly, we herein reaffirm our position that the subject RBCCW containment-isolation valves must undergo. local leak rate-(Type "C") testing per Appendix J'to.10 CFR Part 50.-

Sincerely,

/s/

L Steven A. Varga, Director.

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l

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