ML20210N292

Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits

ML20210N292
Person / Time
Site:	North Anna
Issue date:	08/05/1999
From:	Edison G NRC (Affiliation Not Assigned)
To:	Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
TAC-MA6114, TAC-MA6115, NUDOCS 9908110065
Download: ML20210N292 (6)

Text

(.

August 5, 1999 Mr. J. P. O'Hanlon Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Blvd.

Glen Allen, Virginia 23060

SUBJECT:

NORTH ANNA UNITS 1 AND 2 - APPENDIX B LEAK RATE TESTING METHODOLOGY - TECHNICAL SPECIFICATION BASES CHANGE l (TAO NOS. MA6114 AND MA 6115) ]

l

Dear Mr. O'Hanlon:

By letter dated May 3,1999, you submitted for our information your proposed Technical Specifications (TS) Bases change for " Containment Leakage." You stated that the proposed j changes (enclosure) are being made to allow the use of other NRC staff approved / endorsed J

integrated leak test methodologies to perform containment leak rate testing. 1 Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), Section 59, permits licensees to make changes in the facility as described in the safety analysis report, without prior Commission approval, unless the proposed change involves a change in the TS incorporated in the license or an unreviewed safety question. Your letter stated that it has been determined that these proposed changes do not involve an unreviewed safety question, as defined in 10 CFR 50.59. Accordingly, the regulations authorize you to make the proposed TS Bases changes. Your changes to the Bases may be subject to our future inspections or audits.

Sincerely, Original signed by:

Gordon E. Edison, Senior Project Mana6 Section 1 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339

Enclosure:

As stated

! cc w/ encl: See next page ,,

Distribution: ,

Docket File ; EDunnington ACRS PUBLIC GEdison R. Haag,R!! . ,

\

PDil-1 Reading OGC

%)y \ O DOCUMENT NAME: G:\PDil-1\NORTHANNA\MA6114.wpd (/

'See previous concurrence To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy OFFICE PDll-1/PM k PDll-1/LA* PDil-1/SC NAME GEdison;mw EDunnington REmch DATE / /99 8/14/99 [/[/99

' ^ FICIAL RECORD COPY 9908110065 990805 PDR ADOCK 05000338 P PM

)

[gaasogt e

. UNITED STATES

-g ,y NUCLEAR REGULATORY COMMISSION

'*. WASHINGTON. D.C. 2055H1001 August 5,1999 Mr. J. P. O'Hanlon Senior Vice President - Nuclear Virginia Electric and Power Company ,

5000 Dominion Blvd. i Glen Allen, Virginia 23060 l

SUBJECT:

NORTH ANNA UNITS 1 AND 2 - APPENDIX B LEAK RATE TESTING METHODOLOGY - TECHNICAL SPECIFICATION BASES CHANGE (TAC NOS. MA6114 AND MA 6115)

Dear Mr. O'Hanlon:

By letter dated May 3,1999, you submitted for our information your prcposed Technical Specifications (TS) Bases change for " Containment Leakage." You stated that the proposed changes (enclosure) are being made to allow the use of other NRC staff approved / endorsed j integrated leak test methodologies to perform containment leak rate testing. l Title 10 of the Code of Federa/ Regulations, Part 50 (10 CFR 50), Section 59, permits licensees j

. to make changes in the facility as described in the safety analysis report, without prior Commission approval, unless the proposed change involves a change in the TS incorporated in  ;

the license or an unreviewed safety question. Your letter stated that it has been determined  ;

that these proposed changes do not invo!ve an unreviewed safety question, as defined in 10 CFR 50.59, Accordingly, the regulations authorize you 13 make the proposed TS Brsov  !

changes. Your changes to the Bases may be subject to our future inspections or aud;is.

Sincerely, .  ;

L+ v Gordon E. Edison, Senior Project Manager, Section 1 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339 Enc losure: As stated cc w/ encl: See next page

Mr. J. P. O Hanlon North Anna Power Station Virginia Electric & Power Company Units 1 and 2 cc:

Mr. J. Jeffrey Lunsford . Mr. W. R. Matthews County Administrator Site Vice President Louisa County North Anna Power Station P.O. Box 160 P. O. Box 402 Louisa, Virginia 23093 Mineral, Virginia 23117 Mr. Donald P. Irwin, Esquire Mr. E. S. Grecheck Hunton and Williams Site Vice President Riverfront Plaza, East Tower Surry Power Station 951 E. Byrd Street Virginia Electric and Power Company Richmond, Virginia 23219 5570 Hog Islarsd Road Surry, Virginia 23883 Dr. W. T. Lough Virginia State Corporation Robert B. Strobe, M.D., M.P.H.

Commission State Health Commissioner Division of Energy Regulation Office of the Commissioner P. O. Box 1197 Virginia Department of Health Richmond, Virginia 23209 P.O. Box 2448 Richmond, Virginia 23218 Old Dominion Electric Cooperative 4201 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. J. H. McCarthy, Manager Nuclear Licensing & Operations Support Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, Virginia 23060 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Senior Resident inspector North Anna Power Station U.S. Nuclear Regulatory Commission 1024 Haley Drive Mineral, Virginia 23117 l

I 1

I 1

I i

Technical Specification Bases Changes t

Enclosure

3/4.6 CONTAINMENT SYSTEMS l BASES 3/4.6.1 CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY .

CONTAINMENT INTEGRITY ensures that the release of rad;oactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed ]

i in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

Leakage integrity tests in the containment purge lines and the containment vacuum i ejector system lines is to identify excessive degradation of the resilient seats of these valves. These j tests will be performed in addition to the Type C tests required by 10 CFR Part 50, Appendix J and l will not relieve the responsibility to conform with Appendix J.  !

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, i l

Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, during performance of the periodic test to account for possible degradation l of the containment leakage barriers between leakage tests.

I The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50. The containment is tested by performing leakage rate testing as required by 10 CFR 50 Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163 dated September 1995 or other NRC approved leakage rate testing methodologies.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 and 3/4.6.1.5 INTERNAL PRESSURE AND TEMPERATURE The limitations on containment internal pressure and average air temperature ensure that

1) The containment pressure is prevented from reaching the containment lower design pressure of 5.5 psia for an inadvertent containment spray actuation, l

B 3/4 6-1 Amendment No. 408,1 :6, NORTH ANNA - UNIT 1

3/4.6 CONTAINMENT SYSTEMS BASES i

3/4.6.1 CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY CONTAINMENT INTEGRITY ensures tnat the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

Leakage integrity tests in the containment purge lines and the containment vacuum ejector system lines is to identify excessive degradation of the resilient seats of these valves. These tests will be perfomied in addition to the Type C tests required by 10 CFR Part 50, Appendix J and will not relieve the responsibility to conform with Appendix J.

l 3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P a . A an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L aduring performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the require-ments of Appendix "J" of 10 CFR 50. The containment is tested by performing leakage rate testing as required by 10 CFR 50 Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163 dated September 1995 or other NRC approved leakage rate testing methodologies.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of l

the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1 A and 3/4.6.1.5 INTERNAL PRESSURE AND TEMPERATURE The limitations on containment internal pressure and average air temperature ensure that NORTH ANNA - UNIT 2 B 3/4 6-1 Amendment No. 9499.