ML20155G497

Amend 103 to License DPR-61,renumbering Manual HPSI Throttle Valves in Tech Spec 3.6.B.2 to Be Consistent W/Plant Loop Numbering Scheme

ML20155G497
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/26/1988
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20155G493	List: ML20155G490 ML20155G497 ML20155G503
References
NUDOCS 8806170331
Download: ML20155G497 (4)

Text

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p# 8800

'o UNITED STATES

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3 N E NUCLEAR REGULATORY COMMILION WASHINGTON, D C. 20555

'+, g CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.103 License No. OPR-61

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

A. The application for amendment by Connecticut Yankee Atomic Pcwer (the licensee), dated February 25, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, i as amended (the Act), and the Comission's rules and regulations ,

set forth in 10 CFR Chapter i The facility will operate in conformity with the application, the B.

provisions of the Act, and the rules and regulations of the l Comission; 1

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 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.

l 8806170331 880526 3 DR ADOCK 050

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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. OPR-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.103 , 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.

TO THE NUCLEAL.2EGULATORY COMMISSION

• 'l / r.

ohn . Stolz, Director, rjoectDirectorate1-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Tecnnical Specifications Date of issuance: May 26,1988 e

}'.

ATTACHFENT TO LICENSE AMENDMENT N0.10_3_

. FACILITY OPERATING LICENSE NO. DPR-61 l .

I DOCKET NO. 50-213 l  !

Replace the following page of the Appendix "A" Technical Specifications with i the enclosed page. The revised page is identified by arrendment nurter i and contains vertical lines indicating the areas of change.  !

i Perove Insert  !

3-10b 3-10b l

f f

i l

l

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t i

l l

_ . _ , . . - . _ . . _ - _ _ . _ , _ . _ _ , _ - _ _ , . . _ _ . , _ , ~ . _ _ _ - _ _ _ _

i. , ,.

2) On startup prior to entering Mode 4.

VALVE No. LOCATION ACTION SI-V-905 HPSI loop 1 Valve blocked and locked )

injection line in throttled position.

SI-V-906 HPSI loop 2 Valve blocked and locked j injection line in throttled position.

SI-V-907 HPSI loop 3 Valve blocked and locked l injection line in throttled position. 3 l

SI V 908 HPSI loop 4 Valve blocked and locked injection line in throttled position.

SI MOV-873 Core deluge Valve is locked open line and electrically dis-connected.

• Except as permitted by Technical Specification 4.3.

C.

The following actions shall be taken to disable the High Prgssure Safety Injection Pumps whenever the RCS temperature is below 315 f and the RCS is not vented by a minimum opening of three (3) inches (nominal diameter) or its equivalent:

1.

De energize the HPSI pumps by racking out the breakers and locking the cabinets.

2. Close and lock the HPSI pump discharge valves (SI-V 855A & B).

D.

The following actions shall be taken to disable oge centrifugal charging pump whenever the RCS temperature is below 315 F and the RCS is not vented by a minimum opening of three (3) inches (nominal diameter) or its equivalent.

1. Place the control switch in the trip pullout position.

2. Red tag the switch "D0 NOT OPERATE."

JLAll} I i

This specification assures that adequate emergency core cooling capacity is available whenever the reactor is critical. Based on the loss of coolant accident analysis, exceeding the Interim Acceptance temperature safety limit (2300 F is prevented with only one Criteria high clad pressure safety injection pump in operation. pump and one lo)w pressure safety injec!l Additionally, during the post-LOCA recirculation phase, '

sufficient cooling exists with only one charging, one HPSI, and one RHR pump available. Each of the two trains of emergency core cooling equipment i includes these three pumps. With the pugs associated with both trains of emergency core cooling equipment operable.

3-10b Amendment Nos. /I, /, j)d, f, ,103

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