ML20012C048

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Proposed Tech Specs,Clarifying Spec 3.9.B.3 Re Diesel Generator Operability
ML20012C048
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/09/1990
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20012C045 List:
References
NUDOCS 9003200013
Download: ML20012C048 (6)
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ATTACHMENT I i

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f PROPOSED TECHNICAL SPECIFICATION CHANGE REGARDING CLARIFICATION OF SPECIFICATION 3.9.B.3 (JPTS 83-007) t c

New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50 333 DPR 59 i

9003200013 900309 PDR ADOC:K 05000333

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ATTACHMENT 11 SAFETY EVALUATION FOR THE PROPOSED TECHNICAL SPECIFICATION CHANGE REGARDING CLARIFICATION OF SPECIFICATION 2.9.B.3 (JPTS 83-007) t New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR 59 i

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JAFNPP-3S (cont'd) 4S (cont'd)

3. From and after the time that one of the Emergency Desel 3. The emergency diesel generator system instrumentation l Generator Systems is made or found to be inoperable, shall be checked during the monthly generator test.

continued reactor operation is permissible for a period not

' to' exceed 7 days provided that the two incoming power I sources are available ' and. that the reinsairig Desel Generator System is operable. At the end of the 7-day: .

period, the reactor shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless the affected diesel generator system is made operable sooner.

4. When both Emergency Diesel Generator Systems are 4. Once each operating cycle, the conditions under which the made or found to be inoperable, a reactor shutdown shall Emergency Desel Generator System is required will be be initiated within two hours and the reactor placed in a simulated to demonstrate that the pair of diesel generators cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after initiation of shutdown. will start, accelerate, force parallel, and accept the emergency loads in the prescribed sequence.
5. Once within one hour and at least once per twenty-four hours thereafter while the reactor is being operated in accordance with Specifications 3.9.B.1,3S.82, or 3S.B3 the availability of the operable Erre@.cy Diesel _

Generators shall be &,Towtrated by manual starting and -

force paralleling where applicable.

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l Amendment No. 76,76, [

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I Attachment 11 SAFETY EVALUATION

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1. DESCRIPTION OF THE PROPOSED CHANGES The proposed chango to the James A. FitzPatrick Technical Specifications clarifics the last sentonce of Specification 3.9.B.3 on page 217 as follows: (Affected wording undorlined)

Replace the phraso:

  • unfoss one or both diosol generator systems are made operable soonor" with
  • untoss the affected dicsol generator system is made operable sooner."

The revised Specification will read:

4 *At tho end of tho 7 day porlod, the roactor shall bo placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless the affected diosol gonorator system is made operablo soonor."

The following editorial changos are also included in this chango packago:

Specification 3.9.B.3 Replace the word *Gonoral" in the first sentonco with tho word *Gonorator"; the revised wording will rcad:

  • From and after the timo that one of the Emergency Diosol Generator Systems is ..."

Specification 4.9.B.5 Roplace the word *and* with the word *or"; the revised wording will road:

" operatod in accordance with Specifications 3.9.B.1,3.9.B.2, or 3.9.B.3 tho ..."

II. PURPOSE OF THE PROPOSED CHANGES The intent of Specification 3.9 B.3 is to establish the allowable out of service timo when one diosol generator system is inoperablo, Specification 3.9.B.3 references *both" diosol generator systems.

The applicability of Specification 3.9.B.3 is defined by its opening sentonco which states, 'From and after the timo that one of the Emergency Diosol Generator Systems is made or found inoperable ..." (underline added). The second sentonce of the specification states, "the reactor l shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless one or both diosol generator systems are made operable soonor" (underline added). This chango clarifies this specification by removing the mlsicading reference to *both diosol generator systems."

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SAFETY EVALUATION .

,. .- Page 2 of 3 Specification 3.9.B.4 addressos the actions to bo taken when both Emergency Diosol Generators are inoperable.

The editorial changes to Specifications 3.9.B.3 and 4.9.B.5 are conveniently included with this amendmont packago so as to minimizo unnecessary revisions to technical specification pages.

Ill. IMPACT OF THE PROPOSED CHANGES The proposed changes to the Technical Specifications are purolv oditorial in nature. They clarify Specification 3.9.B.3 by eliminating a misicading statomont and corroct editorial errors in Specifications 3.9.B.3 and 4.9.B.5. The proposed changes do not involve modification of any oxisting equipment, systems, or components; nor do they relax any administrativo controls or limitations imposed on existing plant equipment.

Operation of the plant in accordance with the proposed amendment is not a safety concom. The conclusions of the plant's accident analysos as documented in the FSAR or the NRC Staff's SER are not altered by those changes to the Technical Specifications.

IV. EVALUATION OF SIGNIFICANT H AZARDS CONSIDERATION Operation of the James A. FitzPatrick Nuclear Power Plant in accordanco with the proposed amendment would not involvo a significant hazards consideration as defined in 10 CFR 50.92, since it would not:

1. involvo a significant increase in the probability or consequences of an accident previously evaluated. The proposed changos are puroly oditorial in nature and clarify the Technical Specifications. The proposed changes do not involve modification of any oxisting equipment, systems, or components; nor do they relax any administrativo controls or limitations imposed on existing plant equipment. The changes do not impact previously evaluated accidents; nor do they affect safo plant oporations.
2. croato the possibility of a now or difforont kind of accident from thoso previously evaluated.

The proposed changes are puroly oditorialin naturo, The changes do not involve modification to any of the plant's systems, equipment, or components; nor do they allow the plant to oporate in an unanalyzed condition.

3. Involve a significant reduction in the margin of safety. The proposed changos are putoly oditorialin nature. The changes clarify the requiremont to bo in cold shutdown with an omorgency diosol generator system inoperablo. The existing surveillance requirements and allowable out of service times are unchanged by this proposed amendment. The availability and operability requirements imposed on the Emergency A C Power Systems are, thus, unchanged. The changes do not involvo any plant modifications, nor do they affect the FSAR information regarding the omorgency dicsol generator systems.

In the April 6,1983 Fodora! Rogister (48FR14870), NRC published oxampics of licenso amendments that are not likely to involvo a significant hazards consideration. Example (i) from this Fodoral Register are applicable to those changes and states:

Attachmont il

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  • SAFETY EVALUATION

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  • A putoly administrativo chango to tochnical Specifications: for examplo, a chango to achiovo consistoney throughout the technical specifications, correction of an orror, or a chango in nomenclaturo.*

The proposed changes can be classified as not likely to involvo significant hazards considorations, sinco the changes are purely administrativo in nature and do not involvo hardware changes nor any changos to the plant's safety rotated structuros, systems, or components. The proposed changos are designed to improve the quality of the Technical Specifications.

V. IMPLEMENTATION OF THE PROPOSED CHANGES Implomontation of the proposed changes will not impact the ALARA or Firo Protection Programs at the FitzPatrick plant, nor will the changos impact the environment.

VI. CONCLUSION The changos, as proposed, do not constituto an unroviewod safoty question as definod in 10 CFR 50.59. That is, they:

a. will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safoty previously ovaluated in the safety analysis report;
b. will not increase the possibility for an accident or malfunction of a difforont typo from any ovaluated previously in the safoty analysis report;
c. Will not roduco the margin of safety as defined in the basis for any technical specification; and
d. involvos no significant hazards considoration, as definod in 10 CFR 50.92.

Vll. REFERENCES

1. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Section 8.6.
2. USAEC *Safoty Evaluation of the James A. FitzPatrick Nuclear Power Plant" (SER), dated November 20,1972.
3. USAEC *Supplomont 1 to the Safety Evaluation of the James A. FitzPatrick Nuclear Power Plant" (SER), dated February 1,1973.
4. USAEC "Supplomont 2 to the Safety Evaluation of the James A. FitzPatrick Nuclear Power Plant" (SER), dated October 4,1974.

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