ML20207E504

Amend 88 to License DPR-61,establishing Plant Configuration Assuring That Adequate Cooling Will Be Maintained During Sump Recirculation While Satisfying Single Failure Requirement

ML20207E504
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/24/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207E479	List: ML20207E475 ML20207E504 ML20207E514
References
NUDOCS 8701020193
Download: ML20207E504 (5)

Text

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[ o,, UNITED STATES

! g NUCLEAR REGULATORY COMMISSION

g j WASHINGTON, D. C. 20555

\*****/ CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT

_ DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-61

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

A. The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated December 17, 1986, as supplemented December 19, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Consission; 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 the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance witn 10 CFP Part 51 of the Connission's regulations and all applicable requirements have been satisfied.

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8701020193 861224 PDR ADOCK 05000213 P 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-61 is hereby amended to read as follows:

(2) ,Tychnical Specifications The technical specifications contained in Appendix A, as revised through Amendment No. 88, 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 its date of issuance.

FOR THE NUCLEAR REGULATORY COPWISSION

/1 IO JOK c<o .

v f ristopher . Gri es, Director Integrated Safety Assessment

>h Project Directorate Division of PWR Licensing - B

Attachment:

.. Changes to the Technical

,, Specifications 0

Date of Issuance: December 24, 1986 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 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 3-10 3-10 3-10b 3-10b O

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3.6 CORE COOLING SYSTEMS Anolicability:

Applies to the operating status of the core cooling systems.

Oblective:

To define those limiting conditione for operation that are necessary to insure operability of the core cooling system.

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3eecificatient  !

A) The reactor shell not be critical unless the following conditione are mets

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1) h

' All of the pumps associated with at least one of l the two tralne of einergency core comung i 17'- _ _ E soust be operable. The pumps t assoidated with each train of ereorgency core l

' ' cooling equipment are the solisedge

) rated 7 at feet, f b.

rated at 360 gym at a

c. one kw pressum enesty infection here pump rated at 320 spm at a head

. d. o,= r.shu o heat ,em m ua>

.

• rated et 230 gym at a total head

• Seet.

$ Ataparable.

losst one of two reekbal heat esc @

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3) syst.m valves and Interloche required ser proper operation of coes coding ersteme 8Perable.

5) The followL valves and their operators vlit be positioned as and verified once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />se l

-VALVE NO. LOCATION g

' RH-FCV 402 RHR heat Yelve locIsodla cleoed exchenser tion, Air supply

l bypamIhm

• =d *=r=ver reactor critical and I

- coolant temperature

! ) 3300F.

RH-FCV-796 RHR heat Valves blocke'd in exchanger throttled tlan. Air discherse supply e d when -

. line ever reactor critical and coolant temper-ature > 3300F,

> 3.- 10 Amendment No. y[, , 88

BASIS l j

1 This specification assures that adequate emergency core cooling capacity is i available whenever the reactor is critical. Based on the loss of coolant analysis, melting of the cladding is prevented with only one high pressure safety injection pump and one low pressure safety injection (core deluge) pump in operation.

Additionally, during the post-LOCA recirculation phase, sufficient cooling exists with only one charging, one HPSI, and one RHR available. Each of the two trains of ethergency core cooling equipment includes these three pumps. With the pumps associated with both trains of emergency core cooling equipment operable, substantial margin exists whenever normal power supplies or both diesel generators are available. With only one diesel generator operating and the pumps associated with that diesel operable as required in Item (2) of Specification 3.12 the high pressure safety injection pump and the low pressure safety injection pump, would be started automatically. When the safety injection pumps are operating on off-site power, the charging pump would be started automatically. The RHR and charging pumps would be available for manual start for long-term recirculation cooling.

As described in Reference 3, the RCS OPS, in conjunction with administrative controls, prevents exceeding the temperature and pressure limits in Specification 3.4 while RCS temperature is under 3400F or the RCS is not vented. Part C establishing limiting condition for operation regarding the disabling of the HPSI pumps to further assure that a pressure transient is not initiated. Part D establishes requirements regarding the disabling of a charging pump to assure that a pressure transient is not initiated while retaining the flexibility to establish, under strict administrative controls, a redundant emergency boration path should such action be necessary.

FCV-7961s required to be throttled open within the range specified in and for the

' reasons sited within References (6) and (7). That throttled position has been determinedrecirculation.

post-LOCA by separate analyses to insure acceptable core performance during

REFERENCE:

(2) FDSA Section 3.2.8 (3) D.C. Switzer (CYAPCO) letter to D.L. Ziemann (NRC),

dated May 22,1978.

(4) D.C. Switzer (CYAPCO) letter to D.L. Ziemann (NRC),

dated May 24,1978.

(5) D.C. Switzer (CYAPCO) letter to A. Schwencer (NRC),

dated September 7,1977

, (6) E.J. Mroczka (CYAPCO) letter to C.I. Grimes (NRC), dated

• i December 17,1986. -

(7) E.J. Mroczka (CYAPCO) letter to C.I. Grimes (NRC), dated December 19,1986.

3-10b Amendment No. , ,88

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