ML20117P757

Amend 203 to License DPR-65,allowing Use of performance-based Containment Leakage Testing for Plant, Unit 2

ML20117P757
Person / Time
Site:	Millstone
Issue date:	09/20/1996
From:	Mckee P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20117P759	List: ML20117P757 ML20117P760
References
NUDOCS 9609250297
Download: ML20117P757 (12)

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UNITED STATES g

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 49*****

,o NORTHEAST NUCLEAR ENERGY COMPANY.

THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 203 License No. DPR-65 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Compi. "/, et al. (the licensee) dated January 16, 1996, 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 appli. cation, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health 4

and safety of the public, and (ii) that such activities will be

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conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 1

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2 9609250297 960920 PDR ADOCK 05000336 P

PDR

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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-65 is hereby amended to read as follows:

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(2)

Technical Specifications 1

The Technical Specifications contained in Appendix A, as revised 4

through Amendment No.203, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION l

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/p Phillip F. McKee, Director i

Northeast Utilities Project Directorate Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 20, 1996 4

ATTACHMENT TO LICENSE AMEN 0 MENT NO. 203 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3/4 6-6 3/4 6-6 3/4 6-7 3/4 6-7 3/4 6-11 3/4 6-11 B 3/4 6-1 B 3/4 6-1 6-26

3; 3/4.6 CONTAI M EN SYSTEMS 3/4.6.1 PRIMARY CONTAI MENT

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CONTAIM ENT INTEGRITY LIMITIM C005IT!0N FOR OPERATION i

3.6.1.1 Primary CONTAIVAENT INTEGRITY shall be maintained.

APPLICABILITY: NODES 1, 2, 3 and'4.

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Without primary CONTAIMENT INTEGRITY *, restore CONTAINNENT INTEGRITY within one hour or be in at least !!0T STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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SURVEILLANCE REQUIRENENTS i

j 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

j a.

At least once per 31 days by verifying that all penetrations not capable of being closed by OPERABLE containment automatic isola-j tion valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic j

valves secured in their positions, except as provided in Table l

3.6-2 of Specification 3.6.3.1, i

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At le~ st once per 31 days by verifying the equipment hatch is a

closed and sealed.

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c.

By verifying the containment air lock is OPERABLE per Specifica-t tion 3.6.1.3.

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d.

After each closing of a penetration subject to type B testing 1

(except the containment air lock), if opened following a Type A or 8 test, by leak rate testing in accordance with the Containment Leakage Rate Testing Program.

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• 0peration within the time allowances of the ACTION statements of Specifica-tion 3.6.1.3 does not constitute a loss of CONTAINMENT INTEGRITY.

NILLSTONE - UNIT 2 3/4 6-1 Amendment No. JJ JJ,203 0230

. 2.... T..-.---. m :. n n - W CON AIM EN SYSTENS CONTAIMENT LEAKAGE

, LINITING C0fGITION FOR OPERATION 3.6.I.2 Containment leakage rates shall be liatted to:

An overall integrated leakage rate of <

L., 0.50 percent by l-a.

weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P., 54 psig.

h b.

A combined leakage rate of < 0.60 L, for all penetrations and l

valves subject to Type 8 and C tests when pressurized to P,.

C A combined leakage rate of < 0.017 L, for all penetrations l

c.

V identified in Table 3.6-1 as secondary containment bypass leakage paths when pressurized to P.,

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APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types 8 and C tests exceeding 0.60 L., or (c) with the combined bypass leakage rate exceeding 0.017 L., restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.

2 SURVE!LLANCE REQUIRENENTS 4.6.1.2 The containment leakage rates shall be demonstrated in accordance with the Containment Leakagr Rate Testing Program.

l NILLSTONE - UNIT 2 3/4 6-2 Amendment No. JJJ.177, )W, 203 0238 C.

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NILLSTONE - UNIT 2 3/4 6-3 Amendment No. 77, 171. 203 eaas 1.

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,MJjlSTME - WIT 2 3/4 6-4 Amendment No. JJJ, JJJ, 203

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CONTAllrENT SYSTDis CONTAllglENT AIR LOCKS LINITING COMITICII FOR OPERATION 3.6.1.3 The containment air lock shall be OPERABLE with:

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a.

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Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air j

lock door shall be closed, and 4

b.

An overall air lock leakage rate of 5 0.05 L, at P. (54 psig).

l APPLICABILITY: NODES 1, 2, 3 and 4.

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4 a.

With one containment air lock door inoperable:

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Maintain at least the OPERABLE air lock door closed and either i

restore the. inoperable air lock door to OPERA 8LE status within j

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERA 8LE air lock door closed.

2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least j

once per 31 days.

3.

Otherwise, be in at least NOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and i

in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

4.

Entry

• into an OPERATIONAL MODE or other specified condition under the provisions of Specification 3.0.4 shall not be made j

if the inner air lock door is inoperable.

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b.

With the containment air lock inoperable, except as the result of an i

inoperable air lock door, maintain at least one air lock door l

closed; restore the inoperable air lock to OPERABLE status within i

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in l

COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

i SURVEILLANCE REQUIRENENTS i

i 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE in accordance with the Containment Leakage Rate Testing Program.

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j MILLSTONE - LNIIT 2 3/4 6-6 Amendment No. 7),151,203 osse I

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4 MILLSTONE - UNIT 2 3/4 6-7 Amendment No. 203 orm I

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CONTAlletDIT SYSTEMS SURVEILLANCE REQUIRDIENTS b.

Removing one wire from a dome, a vertical and a hoop tendon checked for lift off force pursuant to Specification 4.6.1.6.1.a and determining that j

over the entire length of the removed wire that:

1.

The tendon wires ars' free of corrosion.

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2.

There are no changes in physical appearance of the sheathing filler grease.

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A minimum tensile strength of 11,760 pounds for at least three i

wire samples (one from each end and one at mid-length) cut i

from enca removed wire. Failure of any one of the wire 1

l samples to mut the niinimum tensile strength test is evidence of abnorar,1 degradation of the containment structure.

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4.6.1.6.2 End Anchoraaer and Ad.iacent Concrete Surfaces T^ne structural 4

integrity of the end anchorages and adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes or degradation has occurred in the visual appearance of the end anchorage i

concrete exterior surfaces or as indicated by the concrete crack patterns l

adjacent to the end anchorages. Inspections of the concrete shall be performed j

concurrent with the containment tendon surveillance (reference Specification j

4.6.1.6.1).

4.6.1.6.3 Liner Plate The structural integrity of the containment liner i

plate shall be determined in accordance with the Containment Leakage Rate i

Testing Program.

4.6.1.6.4 Reports In lieu of any other report required by Specification 6.6.1, an initial report of any abnormal degradation of the containment structure detected during the above required tests and inspections shall be made within 10 days after completion of the surveillance requirements of this specification and the detailed report shall be submitted pursuant to Specification 6.9.2 within 90 days after completion. This report shall include a description of the condition of the concrete anchorages), the ins W ction procedure, the tolerances on(especially at tendon cracking, and the corrective actions taken.

MILL 3T0NE - LNIIT 2 3/4 6-11 Amendment No. JJJ, JJJ, 203 0230

1 3/4.6 CONTAlletENT SYSTEMS BASES i

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3/4.6.1 PRIMARY CONTAINMENT

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3/4.6.1.1 CONTAINMENT INTEGRITY 1

Primary CONTAINNENT INTEGRITY ensures that the release of

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radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restrictien, in conjunc-tion oith the leakage rate limitation, will limit the site 4

bour.cary radiation doses to within the limits of 10 CFR 100 j

during accident conditions.

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3/4.6.1.2 CONTAINMENT LEAKfGE

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The limitations on containment leakage rates ensure that the i

total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of i

P..

As an added conservatism, the measured overall integrated leakage rate is further limited to < 0.75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

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The surveillance testing for measuring leakage rates is in accordance with the Containment Leakage Rate Testing Program.

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i 3/4~.6.1.3 CONTAINMENT AIR LOCKS j

The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and leak rate given in Specifications 3.6.1.1 and 3.6.1.2.

The limitations on the air locks allow entry and exit into and out of the containment during operation and ensure l

through the surveillance testing that air lock leakage will not become excessive through continuous usage.

i NILL; TONE - UNIT 2 3 3/4 6-1 Amendment No. W. 203 03e0 L

J ADMINISTRATIVE CONTROLS 6.19 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established.to implement the leakage rate testing of the primary containment as required by 10CFR50.54 Option B as modified by approved exemptions. (o) and 10CFR50, Appendix J, This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163,

" Performance-Based Containment Leak-Test Program," dated September 1995.

The peak calculated primary Containment internal pressure for the design basis loss of coolant accident is P..

The maximum allowable primary containment leakage rate, L., at P., is 0.5% of primary containment air weight per day.

Leakage rate acceptance critaria are:

Primary containment overall leakage rate acceptance criterion is < l.0 L,.

a.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 L, for the combined Type B and Type C tests, and < 0.75 L, for Type A tests; i

b.

Air lock testing acceptance criteria are:

1.

Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.

2.

For each door, pressure decay is s 0.1 psig when pressurized to 2 25 psig for at least 15 minutes.

The provisions of SR 4.0.2 do not apply for test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of SR 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

I N111 stone Unit 2 6-26 Amendment No. 203 l 0242