ML20235E520

Amend 55 to License DPR-34,revising Tech Spec to Require Both Sections of Both Steam Generators to Be Available for DHR in Power Operation

ML20235E520
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/29/1987
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235E511	List: ML20235E510 ML20235E520 ML20235E528
References
TAC-63576, NUDOCS 8707110095
Download: ML20235E520 (6)

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l PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 l i FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-34

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

A. The application for amendment by Public Service Company of Colorado (the licensee) dated January 15, 1987 as supplemented June 24, 1987, complies with the standards and requirements of i the Atomic Energy Act of 1954, as amended (the Act), and the l Commission's rules and regulations set forth in 10 CFR Chapter I; l 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 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 with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8707110095 870629 PDR ADOCK 05000267 P PDR i

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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.D(2) of Facility Operating License No.

DPR-34 is hereby amended to read as follows:

(2) Technical Specifications j The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective when the Commission approves operation of facility at power levels higher than the 35 percent power currently authorized. The Commission expects that authorization of FSV to operate at power levels up to 82 percent of full power will follow the issuance of this amendment shortly.

FOR THE NUCLEAR REGULATORY COMMISSION i l

OdM &

Jose A. Calvo, Director

{

Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: June 29, 1987

ATTACHMENT TO LICENSE AMENDMENT NO. 55 TO FACILITY OPERATING L5 CENSE NO. OPR-34 -

DOCKET NO. 50-267-l Replace the following page of the Appendix A Technical Specifications with the attached page as indicated. The revised page is identified by amendment number and contains a vertical line indicating the area of change. j 1

Remove Insert l

4.3-1 4.3-1 '

5.3-19 5.3-19 5.3-20 5.3-20 j i

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Fort SR. Vrain Technical Specificatices Amend: .ent , 55 Page 4.3 1 1

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4.3 $ECONDARY REACTCR l00LANT $YSTEM

• LlWI**NG *0ND** ION $ CCR OPER.ATION arolicability l

Applies to the minimum configuration and characteristics of the I

secondary (steam) reactor coolant system, inciscing the steam 1

i generators and turbine plant. f l ]

l Objective To ensure the capability of this system to cool the core and prevent a safety limit from being exceeded by defining the minimum operable eculpment and characteristics of the secondary reactor coolant system.

Specification t.C0 4.3.1 - Steam Generators, Limitiro Conditions for Operatton The reactor small not be crerated at power v n'ess both t*e rereater section are tre economizer-evaporator-s.:erneater-(EES) l section of both steam generators are ope'able for e removal of decay heat.

I The EES sections shall be capable of receiving water f em both

! t*e energency concensate heater and the emergeecy feec= ster )

l *eacer. The reheater sections shall te capable of *eceiving

=ater f rom the emergeecy condensate heacer.

I Basis for (C0 4.3.1 l The stone gecerators provide the means for shutdown heat removal l from the primary coolant. The EE5 section of one steam l g e r.e ra to r is capable of fulfilliag this purpose for $4fe i Shutdown Cooling (refer to FSAR 5ections 10.3.9 and 14.4.2.2),

j as well as providing cooling for other abnormal events. The i reteater sections are capable of providing cooling for other

[ abnormal events, but are not relied upon to provide Safe i Shutcown Coo 11rg. The reheater section can be supplied water l from the emergency concer. sate header and the EES section can be i supplied water from either the emergency concensate heacer or j the teergency fete =4ter rescer.

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J Fort St. Vrain TechnicalSpegfiCations Arnendment

• Page 5.3 19 of one (or more) safety valve (s) of shilar type sad operating cencitions several times c.rieg t-e iaterval j additional conficence in safety valve i will provide reliability and adequate overpressure protection, I

5 specification 52 5.3.10 - secondary Ceclant System Instrumentation Surveillance The seconcary coolant rebeat steam instrumentation used a) for control and indication of emergeecy concensate flow to the repeaters and reheater backpressure, l i  !

I b) to autocratically o;Ln the reheater cischarge by; ass on high pressure, and c) to monitor reFester discharge byoast te :erstyre, and j reaester inlet temperature, shall be functionally tested and calibratec aenwally, or at the cent scheduled plant shutdown if such surveillance I

was not performed during the previous year.

$R 5.3.10 sna11 be implemente cer 151 Criterion B.

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Fort St. Vrain TechnicalSpegficatiers Arnendrr.ent d Page 5.3-20 Basis fe speci<tcation sa 51 :3 I*e freQwency specified for surveillance o' tte aDove

• • strumentation will assure that they perform their espected automatic actions, and that the operator will be l

p ovided with accurste information which he can use to i I avoid abnormal eouipment eseration.

5: edification 5.3.11 - Steam Generator Bimetattic Welds 5,rveillance Se accessible portions of steam generator b{ metallic welds shall be volumetrically examined for indication $ of 5,bsurface defects as follows; a) The main steam ring header collector to main steam piping wele for ore steam gererator mocu'e in each loop at five ca'eacar year intervals, b) The main steam rieg header collector to collector drain piping weld for one steam generator module in each loop at five caleadar year intervals.

) The same two steam gererator mocules initta'ly selectec srall be r:-enamined at each interval, d) The bimetallic weles described in a) and b) shall also be inspected for two other steam generator modules in each loop during the inttial examination,

% $ 8 l