ML20155J611

Proposed Tech Specs Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance

ML20155J611
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/14/1988
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20155J603	List: ML20155J600 ML20155J605 ML20155J611
References
NUDOCS 8810260481
Download: ML20155J611 (7)

Text

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ATTACHMENT 2 PROPOSED CHANGES 8910260481 881014 PDR ADOCK0500g7 P

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. . Fort St. Vrain 01 Technical Specifications

. Amendment No.

Page 5.0-2 Amendment No. 33 by the Nuclear Regulatory Commission.

ISI Criterion C: The surveillance requirement shall be implemented before the beginning of fuel cycle 5.

ISI Criterion D: The surveillance requirement shall be implemented in the existing schedule of surveillance tests, following 90 days from the formal approval date of Amendment No. 33 by the Nuclear Regulatory Commission.

ISI Criterion E: Same as ISI Criterion A but applicable to Amendment No. 51.

ISI Criterion F: Same as ISI Criterion 8 but applicable to fuel cycle 5 and Amencment No. 51.

ISI Criterion G: Same as ISI Criterion 0 but applicable to Amenament No. 51.

I ISI Criterion H: Same as ISI Criterion B but applicable to fuel i cycle 5 and Amendment No .

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Fort St. Vrain 01

, Technical Specifications Amendment No.

Page 5.2-1 5.2 PRIMARY COOLANT SYSTEM - SURVEILLANCE REQUIREMENTS Applicability Applies to the surveillance of the primary (helium) reactor coolant system, excluding the steam generators, and to the surseillance of the reactor auxiliary systems.

Objective To ensure the capability of the components of the primary reactor coolant system to maintain the primary reactor coolant envelope as a fission product barrier and to ensure the capability to cooi the core under all modes of operation.

Specification SR 5.2.1 - pCRV and pCRV Penetration Overpressure Protection Surveillance a) Each of the two overpressure protection assemblies l protecting the PCRV shall be tested in accordance with

[ applicable ASME code requirements to verify their i setpoints.

The PCRV safety valve containment tank closure bolting shall be visually examined for aosence of surface defects when the tank is opened for the above testing.

Tank closure flange leak tightness shall be determined following tank closure. SR 5.2.1.a shall be I implemented per ISI Criterion H.

Fort St. Vrain #1 Technical Specifications Amendment No.

Page 5.2-2 b) Each of the two overpressure protection assemblies protecting a steam generator or a circulator l penetration interspace shall be tested in occordance l with applicable ASME code requirements to verify their j setpoints.

I SR 5.2.1.b shall be implemented per ISI Criterion H.

c) The instrumentation and controls associated with the overpressure protection assemblies in a) and b) above shall be tested and calibrated as follows:

1) The pressure switch and alarm for each interspace -

between a rupture disc and the corresponding safety valve shall be 'unctionally tested monthly '

and calibrated annually.

1 The pressure switch and alarm for che PCRV safety valve containment tank shall be functionally tested and calibrated annually.

SR 5.2.1.c.1 shall be implemented per ISI Criterion D.

2) The position indication circuits associated with the PCRV averpressure protection system shut off l

valves shall be functionally tested and calibrated I l

when testing either of the PCRV overpressure

.. Fort St. Vrain #1 Technical Specifications Amendment No.

Page 5.2-4 The rupture disc is designed to be removed from the system for bench testing. Verification is made of the correct ceflection of the disc at the set pressure level which would cause the membrane to be ruptured. The safety valve is tested for setpoint activation without removing it from the system.

The prassurized portion of the assembly is monitored for leakage during plant operation. Leakage examination of the containment tank cover seals and visual examination of the cover bolts provides assurance that containment tank integrity is restored after the tank cover has been -

re-installed.

Testing of a PCRV penetration overpressure protection assembly can be performed during plant operation since the assemblies are accessible and since LC0 4.2.7 requires only one assembly to be operable at any time.

l The safety valve in each assembly is bench tested or l

l tested in place to demonstrate that it opens at the correct set pressure. The rupture discs are not providsj 1 with a testable design feature and, therefore, cannot be tested. However, one rupture disc of each type assembly l

1 is visually examined to verify that the membrane is free )

of defects and that the knife blade remains sharp.

ATTACHMENT 3 SIGNIFICANT HAZSROS CONSIDERATION

SIGNIFICANT HAZARDS CONSIDERATION l

I. Evaluation The proposed changes would modify SR 5.0, Surveillance  ;

Requirements; SR 5.2.1, PCRV and PCRV Penetration Overpressure Protection Surveillance; and the' associated Basis. The following paragraphs evaluate the changes.  :

t lne new in-service inspection criterion will be added to SR 5.0 to explain implementation requi ements of SR 5.2.1 and allow an  ;

orderly transition to the new suaveillance schedule.

Note: one overpressure protection assembly consists of one  ;

Category C (safety valve) and one Category 0 (rupture disc)

, valve. Category definitions are contained in Subsection IGV or t IWV of the ASME Code,Section XI.  ;

SR 5.2.1.a and SR 5.2.I.b as currently written, require the t overpressure protection assemblies to be tested at intervals not '

to exceed five years, en an alternating basis. Testing in i accordar:e with applicable ASME code requirements would allow -

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4 bench testing or in place testing and include verification of

} setpoints at five year intervals as well as additional testing  !

j for any assembly that failed to function on a regular test.

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) Testing in accordance with proven industry methods and standards will enhance the existing requirements for setpoint verification l and provide additional confidenc'e in the reliability of the overpressure protection assemblies. ,

i The Bssis for SR 5.2.1 has been revised to add the option of either bench testing or in place testing to demonstrate correct

,t set pressure of PCRV penetration safety valves. Either method is acceptable under ASME code requirements. Tests conducted at j Fort St. Vrain have indicated that bench testing, in some cases, i will provide the most reliable and accurate indication of "as I found" relief valve setpoints. '

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II. Conclusion i

Based on the above, operation of Fort St. Vrain in accordance with the proposed changes will not (1) involve a significant increase in the probability or consequences of an accident

, previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of 3 safety. Therefor 6, this change will not create an undue risk to i

the health and safety of the public nor does it involve any significant hazards consideration, i

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