ML20235Z086

Amend 112 to License DPR-61,providing one-time Relaxation of Containment Integrity Tech Specs to Allow Svc Water Side of Four Containment Air Recirculation Fan HXs to Be Cleaned While at Power

ML20235Z086
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/07/1989
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235Z069	List: ML20235Z065 ML20235Z086 ML20235Z088
References
NUDOCS 8903150122
Download: ML20235Z086 (7)

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.' % UNITED STATES I

'%., NUCLEAR REGULATORY COMMISSION 5 E W

• SHINGTON, D. C. 20606 1 u 4..'...* 1 i CONNECTICUT YANKEE ATONIC' POWER COMPANY )

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' DOCKET NO. 50-213 HADOAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.112 License No. DPR-61

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

A. The application for amendment by Connecticut Yankee Atomic Power (the licensee), dated February 10, 1989 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 confomity 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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l 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.(P) of Facility Operating 1.icansa No. OPR-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.112, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMISSION i

J . tolz, Dire or .

P .iect Directora I-4 ivision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l Date of Issuance: March 7, 1989 1

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ATTACHMENT TO LICENSE AMENDMENT NO.112 FACILITY OPERATING LICENSE NO. DPR-61 COCKET NO. 50-213 Peplace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment' number and contain vertical lines indicating the areas of change.

Remove Insert 3-18 3.18 3-19 3-19 3-20 3-20 3-20a 3-20a l

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1 3.11 CONTAINMENT Acolicability: Applies to the operating status of reactor containment, i Ob.iective: To insure containment integrity.

Seccification: A. Leakaue The reactor shall not be critical if the containment leakage exceeds 0.25 weight percent of the contained air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' when extrapolated to 40 psig in .

accordance with Surveillance Standard 4.4.  !

8. Containment Intearitv* t l

(1) Containment integrity shall be maintained l wheneverthegeactorcoolantsystemisabove300 l psig and 200 F. The shutdown margin shall be greater than 2600pcm when the containment is open.

(2) Containment integrity shall not be violated when j the reactor vcssel head is removed unless the reactor cool ant system is borated t: the refueling boron concentration.

1 (3) Positive reactivity changes shall not be made by l rod drive motion or boron dilution whenever the l containment integrity is not intact.

C. Internal Pressure ,

1 The reactor shall not be critical if the containment (

internal pressure exceeds 3 psig, or the internal vacuum exceeds 2.0 psig.

D. Air Recirculation System Three of the four air recirculation units shall be operable whenever the reactor is critical.

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• The service water piping (containment boundary) for each CAR fan heat I exchanger may be opened for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at a time to install or remove i blank flanges. During this time compensatory measures will be taken. If containment integrity is not restored within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, be in H0T STANDBY within 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 following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The cumulative time for the service water piping to be open shall not exceed 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br />. The four CAR fan heat exchangers may be cleaned only once during Cycle 15 under this specification.

3-18 Amendment No. 112

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, E. Containment Sorav system -

l The containment spray system shall be operable whenever the reactor is critical. t F, Containment Ventina-

'(1) Either the containment. air particulate monitoring system or the containment purge exhaust system shall be available at all times when the reactor is critical for post accident' hydrogen venting.

(2) Containment purge capability may be rendered inoperable when the . reactor is critical by placing a blank flange on the 42-inch purge ' air exhaust penetration inside the reactor containment for a period of seven days. If the blank' flange cannot be removed within seven days, then the reactor shall be shut down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

G. The containment isolation valves specified in Table 3.11-1 shall be OPERABLE while in Modes 1, 2, 3, and 4, or:

With one or more of the isolation valve (s) specified in Table 3.11-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either; (1) Restore the inoperable valve (s) to OPERABLE status within four hours, or (2) Isolate each affected penetration within four l hours by use of at least one deactivated automatic valve secured in the isolation l position, or (3) Isolate each affected penetration within four hours by use of at least one closed manual valve or blind flange, or I

(4) Be in at least HOT STANDBY within the next six hours and 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 />.  !

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3-19 Amendment flo.112 l

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H. containment Isolation The Containment Isolation actuation ' system shall be -l l

OPERABLE with the following trip setpoints:

Containment Pressure - HI 1 5 psig PressurizerPressure-LOW $1700psig M: A containment leakage rate of 0.3 weight percent of the contained air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at an internal pressure of 40 psig under hypothetical accident conditions.with 3 of 4 air recirculation filtration units OPERABLE will maintain public exposure within 10 CFR 100 values (see Section 10.4 of the FDSA). y The, reactor coolant system conditions of 300 psig and 200 F sssure that no steam will be formed and hence there would be no pressure buildup in the containment if a reactor coolant system rupture were to occur.

Regarding internal pressure limitations, the containment design pressure of 40 psig would not be exceeded if the internal pressure before a major loss-of-coolant accident is maintained in accordance with Technical Specification 3.11.C. However, 3 psig maximum is sufficient for operations of the continuous leakage monitoring system.

The containment is designed to withstand an internal vacuum of 7.5 psig. The 2.0 psig vacuum is specified as an operating limit to avoid any difficulties with motor cooling.

The design air recirculation flow rate with 4 fags operating under saturated conditions of 40 psig and 261 F is 200,000 CFM. This system is designed to perform its function with only 3 of 4 units in operation. The air filtration system is discussed in detail in FDSA Section 3.6.

The containment spray system in itself can control the containment pressure. It, therefore, provides a backup to the air recirculation system.  ;

Containment post accident hydrogen venting can be accomplished by two methods. One uses the containment air particulate monitoring system and the other uses the containment purge exhaust system. These methods are not required in any short time frame after an accident; it is expected that months may elapse. In any event the systems i used if not operable for maintenance reasons can be readily made OPERABLE providing access into the containment is not required.

3-20 Amendment No. 112

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Containment purge is utilized as a backup means of venting hydrogen from the containment following a loss-of-coolant accident. The containment ' air particulate monitoring system provides the primary means of purging because it p

provides adequate purge flow ' to prevent an explosive

=ixture butidup while allowing fine control of the release of radioactivity during purges. When necessary to effect repairs to the containment purge'or purge bypass isolation valves, a blank flange must be applied to the 42" purge air exhaust penetration inside the reactor containment so' that the containment remains leak tight' This renders the purge' system inoperable for a finite time. Seven days is

-considered a reasonable length of time for repair parts to be received, installed and the system ' retested for leak.

tightness and returned to service.

The OPERABILITY of the containment isolation'. valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation ensures that the release of radioactive material. to the -

environment will be consistent with the assumptions used in the analyses for a LOCA.

The specification to allow containment integrity to be. I relaxed is necessary to allow cleaning of the CAR fan heat exchangers. This specification is only valid prior to the Cycle 15 Refueling Outage.

References:

(1) FDSA Section 3.6.

(2) D. C. Switzer (CYAPCO) letter to A. Schwencer (NRC), dated June 27, 1977, Attachment No. 2.

(3) E. J. Mroczka letter to NRC,' dated February 10, 1989.

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3-20a Amendment No. 112

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