ML20084U604

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Proposed Tech Spec Changes Re Inservice Insp Program,Per Generic Ltr 88-01
ML20084U604
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/15/1991
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20084U600 List:
References
GL-88-01, GL-88-1, NUDOCS 9104220011
Download: ML20084U604 (6)
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ATTACHMENT l PROPOSED TECHNICAL SPECIFICATION CHANGES GENERIC LETTER 88-01 INSERVICE INSPECTi5RhT5UifiEDERW JPTS-88-013 4

1 New York Power Authority -

JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50 333 9104220011 910415 'l gDR AD3CK0500g3

JAFNPP 3.6 (cont'd) 4.6 (cont'd)

F OtiucturalIntegnty F. Structura! Integrity The structural integrity of the Reactor Cochd Syrtem shall be .

N be p uu w on h 1.

rnaintained at the level required by the original acceptance standards throughout the life of the Plant. AS E Mrs mee y M N 1,2 W3 components and supports in accordance with the requirements of the wJd and support inservice inspection program. This inservice inspection program is based on an NRC approved edition of, and addenda to,Section XI of the ASME Boiler and Pressure Vessel Code wtach is in effect 12 rnonths or less prior to the beginning of the inspection interval.

2. An augmented insennce inspection program is required for those high stressed circumfererfdal piping joints in the main steam and feedwater lines larger than 4 inches in diameter, where no restraint against pipe whip is provided.

The augmented in-sennce inspedon prograrn sha!!

consist of 100 percent inspection of these welds per inspection interval.

G- Jet Pumps 3. An Mce IWon Wam for % MM N [

NRC Generic Letter 8&O1 shall be implemented in Whenever the reactor is in the startup/ hot standby or run accordance with NRC staff positions on schedules, modes, all jet pumps shall be operable. If it is determined that a rnettxxis, peisonnel, and sample expansion included in jet pump is inoperable, the reactor shall be placed in a cold this Genenc Letter, or in acordance with attemate condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. measures approved by the NRC staff.

G. Jet Pumps Whenever there is recirculation f'ow with the reactor in the startup/ hot standby or run modes, jet pump operability sha!! be checked daily ty venfying that the following conditions do nnt occursim staneously-Amendment No. [

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ATTACHMENT ll

_ SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES GENERIC LETTER 86-01 INSERVICE INSPECYi6FME5DiMEURWT5 JPTS 88-013 j l

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l New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Dockot No. 50-333 i

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4 7 Attachment 11 SAFETY SVALUATION Page 1 of 3

1. DESCRIPTION OF THE PRGEOSED CHANGES This application for an amendment to the James A. FitzPatrick Technical Specifications incorporates a reference to the NRC rpproved FitzPatrick inservice inspection (ISI) plogram Into the Technical Specifications.

This change adds the followirig statement to Section 4.6.F.3:

An Inservice Inspection Program for piping identified in the NRC Generic Letter 88 01 shall be implemented in accordance with NRC staff positions on schedules, methods, persontwi, and sample expansion includod in this Generic Letter, or in .secordance with alternate measures approved by the NRC staff.

' 11, ' PURPOSE OF THE PROPOSED CHANGES l The NRC staff requested that the Authority incorporate a reference to the existing ISI progrem into the Technical Specifications (Reference 1),

The NRC staff, in Generic Letter 88 01 (Reference 2), requested that licensees add a statement like the one proposed to their Technical Specifications. The proposed statement is similar to the t. ale statement included in the Generic Letter, except for tho phrase '

which permits th( n. of alternate techniques if t.pproved by the NRC.

ill. . EFFECT OF THE m > SED CH ANGES This change is administrative in nature because it amends tr2 Technical Specifications by <

adding a statement which incorporates a reference to the existing NRC approved FitzPatrick ISI program into the Technical Specifications. The conclusions of the FitzPatrick plant's

~ accident analyses as documented in the FSAR or the NRC staff's SER are not altered by this-change to the Tecnnical Specifications.

IV. CVALUATION OF SIGNIFICANY HAZARDS CONSIDERATION Operation of the James A. FitzPatrick Nuclear Power Plant in accordance with this proposed amendment would not involve a significant hazards consideration, as defined in 10 CFR 60.92, since the proposed changes would not:

- 1. -involve a significant increase in the probability or consequence of an accident previously evaluated. This proposed change is purely administiative in nature, ,

since it simpiy incorporates a reference to the existing ISI program into the r

. Technical Specifications. The exhting FitzPatrick ISI program has been

. extensively reviewed and approd by the NRC staff. This change does not involve a modification of any structures, systems, or components; nor does it alter any plant operating procedure or the ISI program.

Attachmont ll SAFET( EVALUATION Pago 2 of 3

2. create the possibility of a now or different kind of accident from thoso provlously evaluated. The proposed chango is purely adminirtrativo in nature, sinco it simp!y incorporatos a reference to the existing ISI program into the Technical Specifications. This chango does not involve a modific@n to any structures, systems, or components. Since the existing ISI program requires no hardwaro changos, the introduction of new failure modos will not occur. Thorofore, this proposad change will not croato any now or difforent kind of accident from those previously evaluated.
3. Involvo a significant reduction in the margin of safoty. The proposed chango is puroly administrative in nature, since it simply incorporatos a roforence to the existing ISI program into the Technical Spoc!fications. The existing FitzPatrick ISI program onsures that suivoillanco is performed on piping susceptible to IGSCC in a manner that increases the probabilP.y of detecting any defects or flaws. This chango doos not involve a modification of any structures, systems, or components; nor does it alter any plant operating procedures or the ISI program.

V, IMPLEMENTATiG OF THE PROPOSED CHANGES Irnplomontation of the propcsod changes will not impact the ALARA or Fire Protection Programs at the FitzPatrick plant, nor will tha changes impact the environment.

VI. CONCLUSION These changes, as proposed, do not constituto an unrovlowed safety question as defined 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 safety previous:y evaluated in the safety analysis report;
b. will not increase the possibility for an accident or malFn: " ' of a difforont typo from any evaluated previously in the safety analysis report,
c. will not reduce the margin of safety as defined in the basis for any technical specification; and
d. involvo no significant hazards consideration, as defined in 10 CFR 50.92.

4 Attachmont 11 SAFETY EVALUATION Page 3 of 3 Vll. REFERENCES

1. NRC letter, D.E. I.aBarge to J.C. Brons dated May 4,1990 regarding the responso to Generic Lotter 88-01, "NRC Position on IGSCC in BWR Austonitic Stainloss Stool Piping" (TAC No. 69136).
2. NRC Generic Lotter 88-01, "NRC Position on IGSCC in BWR Austonitic Stainless Stool Piping' (TAC No. 69136).

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