ML20002C199

Forwards Application for Amend to OL & Statement of Proposed Changes to Tech Specs

ML20002C199
Person / Time
Site:	FitzPatrick
Issue date:	01/06/1981
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Ippolito T Office of Nuclear Reactor Regulation
Shared Package
ML20002C200	List: ML20002C199 ML20002C203 ML20002C206 ML20002C225
References
JPN-81-3, NUDOCS 8101090604
Download: ML20002C199 (3)

Text

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POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMaus CIRCLE NEW YORK. N. Y.10019 (212) 397.6200 Tmuststs GromatT.BEmmy

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JOHN W. BOSTON GEORGE L. ING ALLS vict CHAsawAN ', [',,[',[',f,gg,o, OF Povotn O*s m. flows RICH ARo M. FevNN JOSEPH R. sC IEoER conc =Tr wittoNz' "'**"

January 6, 1981 '" .%*/t Fazernicx a. etanic JPN-81-3 tenov w. siNetAin l'CO", T,

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OFFICE A TMoM As R. FREY Ya*Nll**e"llL'"'

Director of Nuclear Reactor Regulation -

U. S. Nuclear Regulatory Commission > y Washington, D. C. 20555 c_ ,

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Attention: Mr. Thomas A. Ippolito, Chief . . -

g Operating Reactors Branch No. 2 . EC. .~.

Division of Licensing [i'5-; n hl is 5:5

Subject:

James A. FitzPatrick Nuclear Power Plant $ c ~~$

Docket No. 50-333 0 n3 3 Proposed Changes to the Technical SpecificatioMs Related to Miscellaneous Technical Matters

Dear Sir:

- Enclosed for filing are three (3) signed originals and nine-teen (19) copies of a document entitled, " Application for Amendment to Operating License", together with forty (40) copies of Attach-ment I and II thereto, comprising a statement of the proposed changes to the Technical Specifications and the associated Safety Evaluation.

This application seeks to amend Appendix A of the Operating License. The proposed changes would correct and update miscel-laneous technical matters.

A list of the proposed changes to the Technical Specifications is given below:

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@; "f' . ThYs proposed change affects two sections of the

% C- Technical Specifications:

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Section 2.1 Basis 2.1.b (p. 17). The proposed change is in the last sentence of the first paragraph of the right column, and would delete EP Mi O the sentence in its entirety. The mode switch

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((' 2 is currently placed in RUN (on. increasing pres-

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sure) at 825 psig in connection with the MSIV isolation signals. Listing the pressure in p I

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U.S. Nuclear Regulatory Commission the Basis is not relevant to the surveillance requirement 2.1.a.l.b or the LCO on page 8 which permits a change at greater than 785 psig.

b. Section 1.0, Definitions, 1. Modes of Operation,

2. Run Mode (p. 4). The proposed change is third line under Run Mode, and changes "850" to "825". The change is needed to correct the definition and to make it in accordance with the rationale stated above.

2. Section 3.2 Bases (p. 56) . The proposed change is in the first sentence of the last paragraph in the left column, and would change the sentence to read

....ECCS, it causes isolation of Groups A and B isolation valves". The sentence, as now stated, is incorrect, since Group "3" isolation valves do not exist. The FSAR and TS reference define only iso-lation groups A, B, and C. The high drywell pres-sure isolation, for which this section is the basis, specifies, in TS Table 3.7-1, valves in Groups A and B as being isolated by signal "F", which is the high drywell pressure signal. FSAR references are:

Section 7.3.3, Definitions, (p. 7.3-4) and Section 7.3.4.7 (pp 7.3-13 and 7.3-14).

3. Section 3.3 and 4.3 Bases (p. 101). The proposed change would delete the word "..feedwater" from the last sentence of the first paragraph in the right column.

The' Rod Worth Minimizer is connected to sense only steam flow, since feedwater flow at low power is too unstable to use for this purpose.

l 4. This proposed change results from LPCI system modifications and changes:

a. Section 3.6.H.1 (p. 145). Delete Section in its entirety and renumber 3.6.H.2 and 3.6.H.3 as 3.6.H.1 and 3.6.H.2 respectively.

l b. Section 4.6.H.1 (c. 145). Delete Section in its l entirety.

c. Section 3.6.G Bases (p. 155). Delete the last paragraph in the left column.

1 l d. Section 3.6.H Bases (pp 155-156). Delete the I entire right column on page 155 and delete the top paragraph in the left column on page 156.

U. S. Nuclear Regulatory Commission The LPCI loop select logic system was removed from the plant in 1977 and the LPCI system hard piped to reactor recirculation lines. The Design Basis LOCA was reanalyzed by General Electric in NEDO-21662-2 and accepted in USNRC Safety Evaluation in Amendment 30 to JAFNPP Lice: se, September 16, 1977, page 9. The LCO's on page 145 were only to insure proper operation of LPCI loop select as verified by Bases pages 155-156. With the removal cf LPCI loop select, the basis for these LCO's was eliminated. The BWR Standard Technical Specification page 3/4 4-3 and B 3/4 4-1 confirm this as optional LCO for LPCI loop select only.

e. Section 4.5.A.3 (p. 114). The proposed change replaces "... three RHR pumps' in the third line with "... each RHR pump..." and replaces "23,100 gpm" in the fourth line with "9,900 gpm" . These proposed changes result from the LPCI "fix" which effectively split the LPCI mode of the RHR system into two systems. Each pump was modified with a restrictive orifice at discharge to avoid pumps going into runout.

The Authority has classified this application for snendment to the operating license as Class III involving as it does miscel-laneous technical corrections and updates. Furthermore, the application is not deemed to involve a significant environmental hazards considera tion. Enclosed is a check in the amount of

$4,000 as the filing fee per 10CFR Section 170.22, which the

, Authority pays under protest pending a final determination of the l legality of the fee schedule.

Very truly yours,

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enior Vice President

- Nuclear Generation l

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