ML20127E392

Amend 60 to License DPR-21,providing Alternative to Increase in App J,Type a Test Frequency Incurred After Failure of Two Successive Individual Leak Rate Tests

ML20127E392
Person / Time
Site:	Millstone
Issue date:	01/11/1993
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127E376	List: ML20127E372 ML20127E392 ML20127E400
References
NUDOCS 9301190279
Download: ML20127E392 (6)

Text

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1. UNITED STATES .i a~

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, INUCLEAR REGULATORY COMMISSION ~ ]

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HORTHEAST NUCLEAR ENERGY-COMPANY-DOCKET NO. 50-2454  ?

MILLSTONE NUCLEAR POWER STATION. UNIT:1 1 AMENDMENT-T0 FACILITY OPERATING LICENSE:

Amendment No. 60 R License No. DPR-21

1. The Nuclear Regulatory Commission -(the Commission) has found that:-

A. The application for amendment by Northeast Nuclear Energy. Company ~

(the licensee), dated September 29, 1992, _ as supplemented ..

November 6,1992, complies with the standards and requirements of -

the Atomic Energy Act of.1954, as amended (the Act),=and the Commission's rules and regulations set.forth in 10:CFR-Chapter I;'-

B. The- facility will operate -in conformity'with the ' application, the provisions of the Act, and the rules and regulations of the Commission;' - >

C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering- the-health-

'- and safety of the public, and (ii) that such activities will'be conducted in compliance with the Commission's. regulations; D. The issuance of this amendment will not be. inimical- to th'e common.

defense and security or to the health tand safety of the public; ,

and E. The' issuance-of this amendment is intaccordance withL10 CFR Part 51 of the Commission's regulations and all-' applicable requirements..

have been satisfied.

1 R

p_ ADOCK 00000245' PDR

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-21 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 60, are hereby incorporated in the license. l lhe licensee shall operate the facility in accordance with the  !

Technical Specifications. 1

3. This license amendment is effective as of-the date of issuance, to be implemented within 30 days of issuance. i FOR THE NUCLEAR REGULATORY COMMISSION i

John'F. Stolz, Director

[ProectDirectorateI-4 lDiv sion of Reactor Projects - I/II b ice of Nuclear React'or Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 11, 1993 1

ATTACHMENT TO LICENSE AMENDMENT N0i 60 l FACILITY OPERATING tICENSE NO. OPR-21

]

DOCKET NO. 50-245 Replace the following pages of the Appenoix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and H contain vertical lines indicating the areas of change.

Remove insert 3/4 7-4 3/4 7-4 3/4 7-4a l1l 1

B 3/4 7-8 B 3/4 7-8

I.. l

. . LIMITING CONDITION FOR OPERATION 3.7 CONTAINMENT SYSTEMS ,

3.7.A.3, a. Primary containment integrity, as defined in Section 1.0, shall be maintained at all times when the reactor is critical or when the reactor water temperature is above 212'F and fuel is in the reactor vessel,

b. If Specification 3.7.A.3.a cannot be met, initiate an orderly shutdown and have the reactor in the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

~

SVRVEILLANCE RE0VIREMENT 4.7.A.3. The primary containment integrity shall be demonstrated as follows:

a. Integrated Primary Containment Leak Test (IPCLT)

The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 (Total Time Method), BN-TOP-1, and/or the Mass Point Method.

1. Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 t 10 month intervals during serviceshutdown period. atTheP* third test of each set shall be(43 psig) during e conducted during the shutdown for the ten-year plant inservice inspection.

2. If any periodic Type A test fails to meet 0.75 L testscheduleforsubsequentTypeAtestsshall8e,the reviewed and approved by the Commission. If two consecutive Type A tests fail to meet 0.75 L , a Type A test shall be performed at least every 18 mo$ths until two consecutive Type A tests meet 0.75 L,, at which time the above schedule may be resumed.* l

3. The accuracy of each Type A test shall be verified by a supplemental test which:

a. Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L,.

b. Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.

• An exemption from the 18-month accelerated test frequency requirement incurred after the failure of the two successive Type A tests conducted during the Cycle 11 and Cycle 13 refueling outages is allowed.

Millstone Unit 1 3/4 7-4 Amendment No. JJ, JJ, J7,60 00$$

SVRVElllANCE RE0VIREMENT (Continued)

c. Requires the quantity of gas injected into containment or bled from containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P,.

Millstone Unit 1 3/4 7-4a Amendment No. 60 l 0068

4.7 CONTAINMENT SYSTEMS BASES event of a design basis loss of coolant accident. These doses are also based on the assumption of no holdup in the secondary containment resulting in a direct release of fission products from the primary containment through the filters and stack to the environs. Therefore, the specified primary containment leak rate and filter efficiency are conservative and provide margin between expected off-site doses and 10 CFR 100 guidelines.

The fission product source term defined in TID 14844 was also used in the design of facility engineered safety features including shielding and filter sizing.

The maximum allowable test leak rate is 1.2%/ day at a pressure of 43 psig. This value for the test condition was derived from the maximum allowable accident leak rate of about 1.5%/ day when corrected for the effects of containment environment under accident and test conditions.

In the accident case, the containment atmosphere initially would be composed of steam and hot air depleted of oxygen, whereas under test conditions the test atmosphere would be air or nitrogen at ambient conditions. Considering the differences in mixture composition as temperatures, the appropriate correction factor g lied was 0.8 as determined from the guide on containment testing Although the dose calculations suggest that the accident leak rate could be allowed to increase to about 3.0%/ day, before the guideline thyroid dose value given in 10 CFR 100 would be exceeded, establishing the test limit of 1.2%/ day provides an adequate margin of safety to assure the health and safety of the general public. It is further considered that the allowable leak rate should not deviate significantly from the containment design value to take advantage of the design leak-tightness capability of the structure over its service lifetime. Additional margin to maintain the containment in the "as-built" condition is achieved by establishing the allowable operational leak rate. The operational limit is derived by multiplying the allowable test leak rate by 0.75, thereby providing a 25% margin to allow for leakage deterioration which may occur during the period between leak rate tests.

The periodic retest schedule for performing Type A tests is consistent with the requirements of 10CFR50, Appendix J, paragraph !!!.D. If two consecutive periodic Type A tests fail to meet acceptance criteria, 10CFR50, Appendix J, paragraph III.A.6(b) requires an increase in Type A test frequency. However, if Type B and C leakage rates constitute the identified contributor to the failure of the two Type A tests, an exemption to the increased Type A test requirements of 10CFR50, Appendix J, paragraph Ill.A.6(b) may be requested by following the guidance of Information Notice No. 85-71.

(3) TID-20583, " Leakage Characteristics of Steel Containment Vessel and the Analysis of Leakage Rate Determinations."

Millstone Unit 1 B 3/4 7-8 Amendment No. 60 ,

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