ML20125B850

Amend 102 to License DPR-21,permitting Reactor Operation W/Deinerted Reactor Containment Drywell for Up to 48 H to Perform Insp,Equipment Adjustments & Maint

ML20125B850
Person / Time
Site:	Millstone
Issue date:	06/05/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20125B843	List: ML20125B840 ML20125B850 ML20125B860
References
NUDOCS 8506110576
Download: ML20125B850 (7)

Text

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' d' ~q,, UNITED STATES NUCLEAR REGULATORY COMMISSION l . ,I wAsHWGTON, D. C. 20555

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THE CONNECTICUT LIGHT AND POWER COMPANY j WESTERN MASSACHUSETTS ELECTRIC COMPANY I AND NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-245 t

. AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 102 i

License No. DPR-21

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

A. The application for amendment by The Connecticut Light and Power Company, Western Massachusetts Electric Company and Northeast '

Nuclear Energy Company (the licensees) dated May 15, 1985, complies with the standards and requirements of the Atomic

, Energy Act of 1954, as amended (the Act), and the Comission'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 (i) 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 Comission'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 L. E. The issuance of this amendment is in accordance with 10 CFR Part 51 l of the Commission's regulations and all applicable requirements have l_ been satisfied.

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8506110576 850605 PDR ADOCK 05000245 P PDR p ,

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated ir the attachment to this license at:endment and Paragraph 2.Cl?) cf Provisional Operating License flo. DPR-21 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and R as revised through Amendment Mo.102, are hereby incorporated in the. license. The flortbeest Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

. FOR THE tiUCLEAR REGULATORY MMISSI0f!

4c L .! .

John A. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications .

Date of Issuence: June 5,1985

ATTACHMENT TO LICENSE AMENDMENT NO.102 PROVISIONAL OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 l Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT 3/4 7-3 3/4 7-3*

3/4 7-4 3/4 7-4 3/4 7-12 3/4 7-12 B3/4 7-5 B3/4 7-5

• 0verleaf page provided to maintain document completeness. No changes contained on this page.

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o SURVEILLANCE REQUIREMENT LIMITING COND! TION FOR OPERATION

c. Iurus water'ievel Instrumentation d, lit least one of the twc existing narrow shall be colibcated once per 6 rar.ie torus wa ter level monitoring months if both systems are ,

systems shil' be operable whenever opera bl e .

orinar y ca .toinr ent is required, except s

as spec if iec i n 3.7. A.l .e. d. Torus wates level instrumentation

e. If' tne torus water level monitoring system is disabled shall be calibrated once per month and connot be restored in six (6) hours, an orderly if only one syste. is operable.

shutdown shall be initiated and the reactor shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the level monitoring systen is made operable.

2. Drywell to Sunpression Chamber Differential Pretsure

2. Drywell to Suppression Chamber Differential Pressure ,

4.

The differenti.l pressure between the drywei! and

a. Differential pressure between the drywell and suppression chamber shall be recorded once t er suppression chamber shall be maintained equal shift.

to or greater than 1.0 psid, except as specified below.

(1) The differential pressure shall be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering the RUN node, and may be reduced to less than 1.0 psid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown.

(2) The differential pressure may De reduced to sess than 1.0 psid for a maximun. of four (4) hours durinq required operability testino of the torus / reactor building and drywell/ torus votuun teceakers, and during ventinq and r.org i r.<: of the covitaircient.

Anendment No.M 51 3/4 7-3 JbL 6 nm

LIMITING CONDI'? ION FOR OPERATION SURVEILLANCE REQUIREMENT -

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6. Oxygen concentration: 1 6. Oxygen concentration:

a. . After completion of the startup test Whenever inerting is required, the

program and demonstration of plant i primary containment oxygen concentra-electrical output, the primary contain- tion shall be measured and recorded meat atmosphere shall be reduced to on a weekly basis. **

' less than 4% oxygen with altrogen gas whenever the reactor coolant pressure L

is greater than 90 psig and during

' reactor power operation except as -

I specified in 3.7. A.6.b or 3.7. A.6c.

b. Within the 24-hour period subsequent to placing the reactor la the Run mode following a shatdown, the containment

atmosphere orygen concentration shall be reduced to less than 41 by volume 1

and maintained in this condition.

) Delmerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

] prior to a shutdown.

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) c. Oxygen concentration may be greater than i 4% by volume for a period not to exceed

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for purposes of conducting drywell entries relating to testing, 1

surveillances, or maintenance on equipment

, important to safety.

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7. If the specifications of 3.7.A cannot be met, initiate an orderly shutdown and have i

the reactor la a cold shutdown condition j within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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, Amendmer* No. ,)6.j tf . Jai, 102 3/4 7-12 .

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6. Oxygen Concentration '

1 The relatively small' containment volume inherent in the CE-BWR pressure suppression containment and the

] large amount of zirconium in the core are such that the occurrence of a very limited (a percent of so)

reaction of the zirconium and steam during a loss of, coolant accident would lead to the liberation of-sufficient hydrogen to result in a flammable concentration in the containment. Subsequent ignition of the

hydrogen if it is present in sufficient quantities to result in excessively rapid recombination, could result in a loss of containment integrity. .

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The 41 oxygen concentration minimizes the possibility of hydrogen combustion following a loss of coolant accident. Significant quantities of hydrogen could be generated if the core cooling systems did not -

sufficiently cool the core.

, The occurrence of primary system leakage following a. major refueling outage or other scheduled shutdown is j more probable than the occurrence of the loss of coolant accident upon which the specified oxygen concentra-

] tion limit is based. Permitting access to the drywell for leak inspections during a startup is judged i prudent in terms of the added plant safety without significantly reducing the margin of safety. Thus to 1 preclude the possibility of starting the reactor and operating for extended periods of time with significant Icaks in the primary system, leak inspections are scheduled during startup periods, when the primary system

is at or near rated operating temperature and pressure. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period to provide inerting is judged

i. to be suf ficient to perform the leak inspection and establish the required oxygen concentration. The

} primary containment is normally slightly pressurized during periods of reactor operation assuring no air in-leakage through the primary containment. Ilowever, at least once a week, the oxygen concentration will be determined as added assurance.

B. Standby Gas Treatment Systems and C. Secondary Containment j The secondary containment is designed to minimize any ground level release of radioactive materials which might result from a serious accident. The reactor building Provides secondary. containment during reactor operation, when the drywell is scaled and in service; the reactor building provides primary containment when the reactor is i shutdown and the drywell is open, as during refueling. Because the secondary containment is an integral part of l the complete containment system, secondary containment is required at all times that primary containment is j required.

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Amendment IPI ,102 a 3/4 7-5