ML20206D545

Amend 119 to License DPR-59,changing Reactor Vessel Water Level Setpoint Ref Point in Various Tech Spec Pages

ML20206D545
Person / Time
Site:	FitzPatrick
Issue date:	11/10/1988
From:	Capra R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206D550	List: ML20206D545 ML20206D555
References
NUDOCS 8811170127
Download: ML20206D545 (14)

Text

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NUCLE AR REGULATORY COMMISSION W ASHINGTON D. C. 20655 k,...../

POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333

.W'ES A. FITZrATRICK M' CLEAR POWER PLANT AFENDMENT TO FACILITY CPERATING LICENSE knendrent No.1:9 License No. OPR-59 1.

The Nuclear Regulatory Comission (the Cemission) has found that:

A.

The application for amendment by Power Authcrity of the State of New York (the licensee) dated Fay 27, 1988, complies with the standards ard requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comissinn's rules and regulations set forth in 10 CFR Chnter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasenable assurance (il that the activities authorized by this amendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in corpliance with the Comission's regul.' ions; O.

The issuance of this amendrent will not be inimical t ' the cormn l

defense and security or to the health and safety of the >ublic; and E.

The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Comission's regulations and all arplicable requirements have been satisfied.

?.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment. and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amer.ded to read as follows:

5311170127 841110 FER A00cL OS000333 P

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(2) Technical Specifications l

The Technical Specifications centained in Appendices A and B. as revised threugh Amendment No.119. are I

hereby incorporated in the license. The licensee shall i

operate the facility in accordance with the Technical i

Speci fica tions.

3.

This license amendnent is effective as of the date of its issuance.

FOR THE NtlCt. EAR REC 4'LATORY COMMISSION i

h 0* W Re ert A. Capra. Director Project Directorate I-1 I

Civision cf Aeactor Pro,iects. !/!!

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Attachment:

Changes to the Technical Specifications l

i Date ef !ssuance: November 10, 1988

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ATTACHMENT To lirENSE AMENDPENT NO 11o FAC!lffY OPERATING lfCENSE No. DPR-59 DOCKET No. 50-33.1 Revise Appendix A as follows:

Renove Pages insert Paces 11 11 18 18 Ala 41a 55 55 64 64 66 66 67 67 76 76 76a 76a 76d 76d 77 77

g-JAFNPP

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2.1 (cont *d) 4 2.

Reactot_Mattr_Lew_LenLEstm 'idP_StLting l-Reactor low water level scram setting shall be 1177 in, above the top of the active fuel (TAF) l i

at normal operating conditions.

1 i

3.

Tuthlat_SL92_Valyf_C19surt_ SCI @m Trip Setting j

1 Turbine stop valve scram shall be f_10 percent l

valve closure f rom full open when above 217 psig turbine first stage pressure.

4.

Tutkintlontrol Valyt_fnLCinsvIt_ Scram _ T. ria Setting Turbinc *ontrol valve fast closure scram control j

oil pas aure shall be set at 500 < P(850 psig.

S.

L4ein Stre LLint_ Isolation _Valye Closure Scram Iri2_SRLLlD9 Main steam line isolation valva closure scram shall be 110 percent valve closure from full open.

6.

L4alHJttase List _JsQlati9tLYalYt_C191gre on Low Ettshutt When in the run mode main steam line low pressure initiation of main steam line isolation valve closure shalI be > 825 psig.

Am su se rit. No. }4, n, 3g, 119 11

t JAFNPP 2.1 BASES (Cont'd)

c. MRM Flux __ScromJtiILSetLirl_iRxrLMo4cLicent*d).

d. MitM_RosLn19ck Trip _ Setting y

rated power. This reduced flow referenced trip Reactor power level may be varied by moving setpoint will result in an earlier scram during control rods or by varying the recirculation slow thermal transients, such as the loss of flow rate.

The APRM system provides a control 80*F feedwater heating event, than would result rod block to prevent rod withdrawal beyond a with the 120% fixe 4 high neutron flux ceram given point at constant recirculation fine rate, trip. The lower fle.a referenced scram setpoint and thu3 prevides an added level of protection therefore decreases the severity (.a CPR) 32 a before APRM Scram. This rod block trip setting, slow thermal transient and allows lower Opt;ra-which is automatically varied with recirculation ting Limits if such a transient is the limiting loop flow rate, prevents an increase in the E.bnormal operational transient during a catrtain reactor power level to excessive values due to exposure interval in the cycle.

control withdrawal. The flow variable trip setting parallels that of the APRM Scram and The APRM fixed high neutron flus sigcol does not provides margia to scram, assuming a steady-incorporate the time constant, but responds state operation at the trip setting, over the directly to instantaneous acutron flux.

This entire recirculation flow range. The actual scram setpoint scrams the reactor during fast power distribution in the core is established by power increase transients if credit. is not taken specified control rod sequences and is moni-for a direct (position) scrami, and al:o serves tored continuously by the in-core LPRM uystem.

to scram the reactor if credit is not takee for As with the APRM scram trip setting, the APRM the flow referenced scram.

rod block trip setting is adjusted downward if the maximus fraction of limiting power density The scram trip setting must be adjust 3d to exceeds the fraction of reted [.ower, thus pre-ensure that the LHCR transient peak is not serving the APRM rod block margin. As with the increased for any combination of maximum scram setting, this may be accompl.shed by traction of limiting power density (MFLPD) and adjusting the APRM gain, reactor core thermal power.

The scram setting is adjusted in accordance with the formula in 2.

Reactor %Lnr_Jow LeytLScm_IripJetting l

Specification 2.1.A.I.c, when the MFLPD is greater than the fraction of rated p3wer (FRP).

The reactor low water level scram is set at a This adjustment may be accomplished by either point which will assure that the water level (1) reducing the APRM scram and rod block set-used in the Bases for the Safety Limit is tings or (2) adjusting the indicated APRM signal maintained. The scram setpoint is based on to retlect the high peakir.g condition.

normal operating temperature and pressure conditions because the level instrumentation is Analyses of the limiting transients show that no density compensated.

scram adjustment is required to assura that the MCPR will be greater than the Safety Limit when the transient is initiated from ths NCPk oper-aLing limits pravided in Specitication 3.1.11.

Ame mhaent tio. 34, 119 I ll

t JAFNPP TAILLE._3Al. (contd)

R E ACTQR_ EROTEG I OLsy SIf.M_1fiCR eM ) I1sSTRIMELNIAI19N_REQulREME!fI Minimuse No.

Modes in WI.ich Total of Operable Trip Level Function Must be Number of l

Instrument Trip Function Setting Operable Instrument Action Channels Channels (1) per Trip Refuel Startup Run Provided Systeem (1)

(6) by Desiga for Both Trip Systems 2

APRM Downscale 1 2.5 indicated on X

6 Instrusment A or B scale (9)

Channels 2

High Reactor 1104S psig X(8)

X X

4 Instrument A

Pressure Channels 2

High Drywell 12.7 psig X(7)

X(7)

X 4 Instrument A

Pressure Channels 2

Reactor Low Water 2 177 in. above TAF X

X X

4 Instrument A

Level Channels I.

3 High Water Level

(_34.5 gallcas per X(2)

X X

Instrument A

in Scram Discharge Instrument Vc-lu:ne hannels VoIune 2

Main Steam line (3x norwl full X

X X

4 Instrument A

High Radiation power bacaground (16)

Channels j

4 Main Steam Line f_10% valve X(3)(5)

X(3)(5)

X(SJ 8 Instrument A

Isolation valve closure Channels l

Closure j

i i

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Amendment No. MI, d, ta, N, 97, 96, 119 j

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3. 2 34 3y,3 In addition to reactor protection instrumentation has a direct bearing on safety, are chosen at a level which initiates a reactor

..m.

protective lastru-away from the normal operating range to prevent laad-mentation has been provided whach laitiates action to vertent actuation of the safety system involved and mitigate the consequences of xcidents which are exposure to abnormal riituations.

beyond the operator's ability to control, or teremi-mates operator errors before they result in serious Actuation of primary containment valves is laitiatM consequences.

This set of specifications ptcvides by protective instrumentation shown in Table 3.2-1 the limitlag conditions of operation for the primary which senses the conditions for which isolation is s

system isolation function, initiatica of the Core required.

Such instrumentation must be available Cooling Systems, Control Bod Block and Standby Cas whenever primary containment integrity is required.

Treatment Systems. The objectives of the specifica-tions are to assure the effectiveness of the protec-The instrumentation which initiates primary. system tive instrumentation when

required, even duricq isolation is connected la a dual bus arrangement.

periods when portions of such systems are out of service for malatemance, and to prescribe the trip The low water level instrumentation, set to trip at settiaqs required to assure adequate performance.

177 in. above the top of the active fuel, closes all When accessary, one channel may be made inoperab?e isolation valves except those la Group 1.

Details of for brief intervals to conduct required functional valve grouping and required closing times are given tests and calibrations.

in Specification 3.7.

For valves which isolate at this level, this trip setting is adequate to prevent Some of the settings on the lastrumentation that uncovering tha core in the case of a break la the initiate or control core and containment coolino have largest line assuming a. 60 sec. valve closing time.

tolerances esplicitly stated where the high and low Beguired closing times Are less than this.

values are both critical and may have a substantial effect on safety. The set points of other instrumen-The low-low reactor water level instrumentation is tation, where only the high or low eM of the setting set to trip when reactor water level is 126.5 in.

above the top of active fuel. This trip Amendment No. Mrf, 119 55

r JAFNPP TABLE 3.2-1

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INSTRUMENTAT10M_TtfAT_ItarIIATgS_ PRIMARY CQNTh{NMENLJSQLAllQN Minimum Number of Total Number of Instrument Operable Instrument Channels Channels Provided by Design Action PeL_Tdu Sntep_J1)

Instrw=ent Trip _L ucl Setting for DottLTrie_Synema (2) 2 (6)

Reactor Low Water 2177 in. above TAF 4 Inst. Channels A

Level 1

Reactor High Pressure < 75 psig 2 Inst. Channels D

(Shutdown Cooling Isolation) 2 Reactor Low-Low-Low 2_18 in. above TAF 4 Inst. Channels A

Water Level 2 (6)

High Drywell Pressure < 2.7 psig 4 Inst. Channels A

2 High Radiation Main I3xHormalRated 4 Inst. Channels B

Steam Line Tunnel Full Power Background (9) 2 Los Pressure Main 2825 1.sig (7) 4 Inst. Channels B

Steam Line 2

High Flow Main Steam I140% of Rated Steam 4 Inst. Channels B

Line Flow 2

Main Steaza Line Leak I_40*F above max 4 Inst. Channels B

Detection high ambient Temperature 3

Reactor Cleanup Sys -

I40*F above mau 6 Inst. Channels C

tem Equipment Area

mbient High Teeperature Low Condenser Vacuum 18" Hg. Vac (8) 4 Inst. Channels B

Closes MSIV's hemLacnt No. L1, W, 4e. trir. so, apa, 119 64

s JAFNPP IADLE 3.2-2 IMSIBL9fdfTATION THAL JMIDATESELCOMTROI,S_THE CORE AND COHTALNMJHT C00 LING SYSIEMS Minimum No.

Total of Operable Number of Instru-Instrument ment Channels Pro-Item Channels Per vided by Design for

_Mo.

Trip System (1)

Trio Function Trip Level Settina Both Trip Systems Remarks 1

2 Reactor Iae-Low 1126.5 in. above TAT 4 HPCI & RCIC Initiates HPCI, Water I4v51 Inst. Channels BCIC & SGTS.

2 2

Reactor Low-Low-118 in. above TAF 4 Core Spray & RHR Initiates Core Spray, Low Water Level Instrument Channels LPCI, and Emergency

(

Diesel Generators.

i 4 ADS Instrument Initiates ADS la conjunc-Channels tion with confirmatory low level, 120 second time delay and LPCI or Core Spray pump discharge pressure interlock if not inhibited by ADS override switches.

3 2

Reactor High Water I222.5 in. above TAF 2 Inst. Channels Trips HPCI Turbine and Level closes RCIC steam line isolation valve.

4 1

Reactor Low Level 1 0 in. above TAF 2 Inst. Channels Prevents inadvertent

(

(inside shroud) operation of contain-ment spray during accident condition.

Amena ent %.

IAr, y 64 64 119 66

l A

JAFNPP table 3.2-2 (cont'd)

IMSTRUIENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No.

Total

)

of Operable Number of Instru-Instrument ment Channels Pro-Item Channels Per vided by Pesign for No.

Trip System (I)

Trip Functinn Trip Level Setting Both Trip Systems Remarks i

5 2

Containment High 1< p<2.7 psig 4 Inst. Channels Prevents inadvertent Pressure operation of containment spray during accident condition.

1 I

6 1

Confirmatory Low

[I77in. above TAF 2 Inst. Channels ADS Permissive in Level conjunction with Reactor Low-Low-Low Water Level.

7 2

High Drywell b2.7psig HPCI Inst. Channels Initiates Core Spray Pressure LPCI. HPCI and SCTS.

O 2

Reactor Low Pres-1450psis 4 Inst. Channels Permissive for opening i

sure Core Spray and LPCI Admission valves.

A Amendment No. 14. A8. F1. 74. 119 67

a, TA3!

L Z:4 SUBYEILI4NCE 3HSTRUMENTAIIDM 4

MSnimun No.

of sp rable No. of Channels Instrument Type Indication Provided Channels Instrument and Ranoe by Dealga Action Barrow Range Reactor Level Indicator (13) (2)

(Note 3) 164.5 to 224.5 in. above TAF 2

Marrow Range Recorder 3

Reactor Level 164.5 to 224.5 in. above TAF (Note 4)

Wide Range 1

Reactor Level Indicator (2)

(Note 14) 14.5 to 224.5 in. above TAF 2

• fide Range Indicator-Recorder Reactor Level 14.5 to 224.5 in. above TAF (Note 15) 1 Fuel Zone Indicator (2)

Reactor Level 150 in. below to 200 in.

(Note 16) above TAF 2

Fuel Zone Indicator-Recorder Reactor Level 150 in below to 200 in.

(Note 17) above TAF Reactor Pressure Indicator (Note 5) 0-1200 psig 2

Reactor Pressere Recorder 5

(1) (2)

(Note 6) 0-1200 psig i

Amendment No. 18, g, yf, Ff, p4, 119 76 j

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TApkE 3.2-6 (Cont *d)

A SilRYIILLAMCE IMSIEUMEttTATION Minismusa No.

of Operable No. of Channels Instruneet Type Indication Provided Channels Instrussent and Range by i)esign Action Drywell Pressure (Narrow Range)

(Narrow Rasge)

Indicator Recorder 10 - 19 psia 1

Drywell Pressure (Wide Range) 2 (2)

Indicator Recorder 0 - 100 psia Drywsill Temperature Indicator 50 - 250*r 2

4 (1) (2)

Drywell Temperature Recorder 50 - 350*r Supprescion Chamber Indicator Temperaturo 50 - 250*r 2

4 (1) (2)

Suppression Chasaber Recorder Temperature 50 - 350*r Amendment No. Yf, W, H, 119

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t ISQIES FOR TABLE 3.2-6 (COtrTINUED_1

14. One (1) indicator from reactor wide range level instrument channel A.

15. One (1) indicator-recorder irom reactor wide range level instrument channel B.

16. One (1) ladicator from reactor fuel zone level instru: ment chamael A.

17. One (1) indicator-recorder from reactor fuel some level instrument channel B.

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Amendment No.119 76d 5

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JAFNPP TABLE 3.2-1 I p itNTATION THAT IMITIATES RECIRCULATION PUMP TRIP Cinimum mWe of Total Number of Instrument Operable Instrument Channels Provided by Channels per trip Design for Both System (1)

InstC*Jeant Trip Level Setting Channels Action 1

Reactor High Pressure

[1120psig 4

(2) 1 2,asetor Low-Low 1126.5 in. above tar 4

(2)

Sr1er Level Notes for Table 3.2-7 1.

Whenever the reactor is in the run mode, there shall be one operable trip system for each parameter for each operating recirculatica pump.

From and after the time it is found that this cannot be met, the indicated action shall be taken.

2.

Reduce power and place the Mode Selector Switch in a Aode other than the Run Mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment No. 6f. JK,119 11

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MSHINGTON. D. C. 20555

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SAFETY EVALUATION BY THY OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 119 TO FACILITY OPERATING LICENSE NO. OPR-59

'{ IER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICV, NUCLEAR POWER PLANT DOCKET NO. 50-333 1.0 Ify.000CTION Ry letter dated May 27,1988 (Peference 1), the Power Authority of the State of New York (PASNY) requested chances to the Yechnical Specifications for James A. Fitzpatrick Nuclear Power Plant. The changes update the Technical Specification for the reactor water level instrumentation modifications that were proposed to comply with the requirements of NUREi:-0737 and Regulatory Guide 1.91. The proposed modifications were found acceptable in our letters to PASNY dated February ?6,1982 (Reference 21. December 19, 1986 (Reference 3), March 16, 1983 (Reference 4), and March 14, 1988 (Reference 5).

References ? and 3 included changes to the Technical Specifications (Amendment Nos. 67 and 103, respectively, to the facility operating license) incorporatino modifications to reactor water level instruments setpoints. The proposed changes to the Technical Specifications consist of rewording on five tables (Tables 3.1-1, 3.9-1, 3.?-?, 3.2-6, 3.?-7) and three pages (11, 18, 551 for the consistency of nomenclature and updating Tables 3.2-? and 3.2-6 to incorporate modifications that were found acceptable in References 4 and 5.

2.0 EVALUATION The proposed changes involving rewording for consistency o' nomenclature are only administrative. The technical adequacy of these chances were found acceptable in References 2 and 3.

The proposed changes to incorporate modifications approved in References 4 and 5 are as follows:

(1)

Item II.K.3.13 of NUREG-0737 required modifications to RCIC initiation logic to perinit automatic RCIC restart on reactor low water level following its trip on reactor high water level. The existing logic closes RCIC turbine trip valve on reactor high water level. The licensee's studies determined that compliance to the NUREG requirement can be achieved by modifying the logic to close the RCIC steam line isolation valve in lieu of RCIC turbine trip valve on reactor high water level. The staff evaluation in Reference 4 found this modification acceptable.

The proposed change in Table 3.2-2 of the Technical Specification reflects this modification and is, therefore, acceptable.

, (?) As part of the modifications to implement Regulatory Guide 1.97 requirements, the licensee proposed to recalibrate the reactor water level fuel zone instrument to cover a wider range that will include full active length of fuel, and to add a water level indicator-recorder to one of the two channels of the reactor water level wide range instrument.

The staff evaluation in Reference 5 found these modifications acceptable.

The proposed changes in Table 3.2-6 reflect these modifications and are, therefore, acceptable.

Based on the above evaluation, the staff concludes that the proposed changes to the technical specifications represent the modifications thet were r

previously aoproved by the staff, do not involve an unreviewed safety ouestion and, therefore, are acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public coment on such finding. Accordingly, onis amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Sec 51.22(c)(9).

Pursuant to 10 CFR 51.??(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

4.0 CONCLUSTON We have concluded, based on the considerations discussed above, that: (11 there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public, i

5.0 REFERENCES

1.

PASNY letter (John C. Brons) to NRC, dated 5/27/88, i

i 2.

NRC Letter (Phil J. Polk) to PASNY (Leroy W. Sinclair1 dated 2/26/82.

3.

NRC Letter (Harvey Abelson) to PASNY (John C. Brons) dated I?/19/86, 4

NRC Letter (Dominic B. Vassallo) to PASNY (Leroy W. Sinclair) dated 3/16/83.

5.

NRC Letter (Harvey Abelsoni to PASNY (John C. Brons) dated 3/14/88.

Dated: !;ovember 10, 1988 PRINCIPAL CONTRIBUTOR:

I. Ahmed i

Novembst 10, 1988 Docket No. 50-333 DISTRIBUTION Docket F1 T NRCPDR Local PDR PDI-1 Rdg SVarga BBoger CVogan DLaBarge Mr. John C. Brons OGC DPagan Executive Vice President - Nuclear Generation EJordan BGrimes Power Authority of the State of New York TBarnhart (4) WJones 123 Main Street ERutcher GSchwenk White Plains, New York 10601 ACRS (10)

GPA/PA ARM /t.FMB JJohnson, RI

Dear Mr. Brons:

IAhmed RCapra The Comission has issued the enclosed Amendment No.119 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TS) in response to your application transmitted by letter dated May 27, 1988 (TAC 68320).

The amendment changes the reactor vessel water level setpoint reference point in various TS pages from the bottom of the steam separator skirt to the top of the active fuel and changes the RCIC turbine trip to a steam line isolation on high reactor water level.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will he included in the Comission's next reaular bi-weekly Federal Register notice.

Sincerely, original signed by David E. LaRarge, Project Manaper Project Directorate I-1 Division of Reactor Pro.iects, I/II

Enclosures:

1.

Amendment No.119 to DPR-59 2.

Safety Evaluation ec: w/ enclosures See next pace J

PDI b PDI-1[V PDI-1 OGC NjA CVogan OlaRarge:vr RCapra

% /88 $/](/88

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e Mr. John C. Brons Jenes A. FitzPatrick Nuclear Power Authority of the State of New York Power Plant cc:

Mr. r-erald C. Goldstein Ms. Donna Ross Assistant General Counsel New York State Erergy Office Power Authority of the State

? Empire State Plaza of New York 16th Floor 10 Columbus Circle Albany, New York 1??23 flew York, New York 10019 Resident Inspector's Office U. S. Nuclear Regulatory Comission Regional Administrator, Pegion !

Post Office Box 136 U.S. Nuclear Regulatory Connission Lycomino, New York 13093 475 Allendale Road King of Prussia Pennsylvania 19a06 Mr. Radford J. Converse Mr. A. Klausman Resident Manager Senior Vice President - Appraisal James A. Fit: Satrick Nuclear and Compliance Services Power Plant Power Authority of the State Post Office Box 41 of New York Lycomino, New York 13093 10 Columbus Circle New York, New York 10019 Mr. J. A, Gray, Jr.

Mr. George Wilverding, Manager Director Nuclear Licensing - BWR Nuclear Safety Evaluation Power Authority of the State Dower Authority of the State.

of New York of New York 123 Main Street 123 Main Street White Plains, New York 10601 White Plains, Ner York 10601 Fr. Robert P. Jones, Supervisor Mr. R. E. Beedle Town of Scriba Vice President Nuclear Support R. D, #4 Power Authority of the State Oswego, New York 13126 of New York 123 Main Stre t Mr. J. P. Bayne, President White Plains, New York 10601 Power Authority of the State of New York Mr. S. S. Zulla 10 Columbus Circle Vice President Nuclear Engineerino flew York, New York 10019 Power Authority of the State nf New York Mr. Richard Patch 123 Main Street Cuality Assurance Superintendent White Plains, New York 10601 James A. Fit 2 Patrick Nuclear Power Plant Mr. R. Burns Post Office Box 11 Vice President Nuclear Operations Lycomino, New York 13093 Power Authority of the State of New York Charlie Donaldson, Esouire 123 Main Street Assistant Attorney General White Plains, New York 10601 New York Department of Law 120 Brcadway New York, New York 10271

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NUCLEAR REGULATORY COMMISSION 3

WASHING TON, D. C. 20656 POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 1AMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMfNT TO FACILITY OPERATING LICENSE Amendment No. 119 License No. DPR-59 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated May 27, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CF1 Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment ccn be conducted without endancering th health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D,

The issuance of this amendment will not be inimical to the cwinon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordan:e with 10 CFR Part 51 of the Comission's regulations and all applicable reouf rements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(?) of Facility Operating License No. DPR-59 is hereby amended to read as follows:

n.

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(2) Technleal Specifications _

The Technical Specifications contained in Appendices A and B, as revised througit Amendtnent No.119, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i

M a.C w Re ert A. Capra, Director Project Directorate I-1 Division of Reactor Proiects. I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: November 10, 1988 l

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ATTACHMENT TO LICENSE AMEN 0 MENT NO.119 FACILITY OPERATING LICENSE NO. 00R-59 DOCKETNO.50-3R j

l Revise Appendix A as follows:

i Remove Pages insert Pages

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11 11 18 18 41a dia 55 55 64 64 66 66 67 67 76 76 76a 76a 76d 76d 77 77

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i JAFNPP 2.1 (cont'd) 2.

Reactor __ Water Jaw _LeycL ScramjijlLS2LtiD9 l

Reactor low water level scram setting shall be M_177 in. above the top of the active fuel (TAF) l at normal operating conditions.

3.

Turbine _Stos_Yalyc_ Closure _Scrom_ Trip settima Turbine stop valve scram shall be,{l0 percent valve closure from full open when above 217 psig turbine first stage pressure.

4.

Tu rb i ec_. Con t re l_va l yt_fe a t_ Cl os ur e_Scr asLTrie Setting Turbine control valve fast closure scram control oil pressure shall be set at 500 ( P(850 psig.

5.

Mein _Strom. Lint _lsolatierLYalve Closura_ Scram Trie_ Setting Main steam line isolation valve closure scram shall be 1 10 percent valve closure from full open.

6.

Me i nJ te an__L inol a91 s ti o n _va l yn._C le mur a_n a _Lew Pressure When la the run mode main steam line low pressure initiation of main steam line isolation valve closure shall be 2 825 psig.

Ama n=lme sit N.e. 34 M,

y, 119 11

JAft4PP s.

2.1 BASES (Cont *d)

c. APIM lln_Screm Jtip_Sct(ing (Run. Mode) (cynt*d)

d. APFM Rgtpl9ck_Tric_ Setting rated power.

This reduced flow referenced trip Reactor power level may be varied by moving setpoint will result in an earlier scram during

~

control rods or by varying the recirculation slow thermal transients, such as the loss of flow rate.

The APRM system provides a control 80*r feedwater heating event, than would result rod block to prevent rod withdrawal beyond a with the 12 % flued high neutron flus scram given point at constant recirculation flow rate, trip. The lower flow referenced scram setpoint and thus provides an added level of protection therefore decreases the severity ( A CPR) of a before APRM Scram. This rod block trip setting, slow thermal transient and allows lower Opera-which is automatically varied with recirculation ting Limits if such a transient is the limiting loop flow rate, prevents an increase in the abnormal operational transient during a certain reactor power level t2 excessave values due to exposure interval in the cycle.

control withdrawal. The flow variable trip setting parallels that o' the APRM Scram and The APRM fixed high neutron fleu signal does not provides margin to scram, assuming a steady-incorporate the time constant, but responds state operation at the trip setting, over the directly to instantaneous neutron flux.

This entire recirce Mion flow range.

The actual scram setpoint scrams the reactor during fa t power distribution in the core is established by power increase transients if credit is not taken specified control rod sequences and is moni-for a direct (position) scram, and alsa Jerves tored continuously by the in-core LPRM system.

to scram the reactor it credit is not taken for As with the APRM scram trip setting, the APRM the flow referenced scram.

rod block trip setting is adjusted downward if the maximum fraction of limiting pcwer density Ths scram trip setting must be adjusted to exceeds the fraction of rated power, thus pre-ensure that the LHCR transient peak is not serving the APRH rod block margin.

As with the increased for any combination of maximum scram setting, this mal be accomplished by it.)ction of limiting power density (MFLPD) and adjusting the APRM gain.

reactor core thermal power. The scram setting is adjusted in accordancre.ith the formula in 2.

Ec o cto t_w te r_Lowleyc L Sc r om lr i p Jc tti ng l

o Specification 2.1.A.I.c, when the NFLPD is greater than the frection of rated power (FRP).

The reactor low water level scram is set at a This adjustner.t may be accomplished by either point which will assure that the water level (1) reducing the APRM scram and rod block set-used in the Bases for the Safety Limit, is tings or (2) adjusting the indicated APRM signal maintained. The scram setpoint is based on L.

retlect the high peaking condition.

normal operating temperature and pressure conditions because the level instrumentation is Analyses of the limiting transients show that no density compensated.

scram adjustment is required to assure that the Wl'at will be greater t ima the Safety Limit when the transient is initiated from the MCPM oper-ating limits provided in Specification 3.4.is.

Ame n.t e nt iso. 34 I19 iH

JeFMPP TAM-tL3. '. * (conCdl

~'

FEACIOR_fROTECTIOM_SYSIfM_(SCRAMLlNSTRUMEMIATID* REQUIREMEt8T Micious No.

Modes in which Total af Operable Trip Level Function Must be Number of I

Icctrumeat Trip Function Setting Operable Icstrument Action Chaamels Channels (1) per Trip Refuel Startup Rua Provided Syctem (1)

(6) by Design for Both Trip Systems 2

APRM Downscale 1 2.5 indicated on X

6 Instrument A or 8 scale (9)

Channels 2

High Reactor 11045 psig X(s)

X X

4 Instrument A

Pressure Channels 2

High Drywell 1 2.7 psig X(7)

X(7)

X 4 Instrument A

Pressure Channels

?

Reactor Low Mater 2177 in. above TAF X

X X

1 Instrument A

Level n'hannels 3

High Mater Level

(_34.5 gallons per X(2)

X X

S estrument A

la Scram Discharge Instrument volume Cha,oels Volume 2

Main Steam line

[3a monnal full X

X X

4 Instrument A

High Radiation power backgrour.d (16)

Chamaels l

4 Main Steam Line

(_10% valve X(3)(5)

X(3)(5)

X(5) 3 Instrument A

l Isolation valve closure Chaamels Closure Ame asment No. nf, W1, 84, M. 87 9d, 119 414 l

_. ~. - - -.. - _ _

. _ ~ -

~.

s s.

JAFMPP i

l 3.2 hsES l

i l

5 addition to reactor protection instrumentation har a direct bearing on safety, are chosen at a leval l

l which id tiates a reactor.

..m. protective instru-away from the normal operating range to prevent imad-mentation has da provided whach lettiates action to vertent actuation of the safety system involved and mitigate the consege-ecas of accidents which are exposure to abnormal situations.

beyond the operator's abilley te control, or termi-mates operator errors before they result in serious Actuation of primary containment valves is initiated

)

l consequences.

This set of specifications provides by protective lastrumentation shows la Table 3.2-1 the limiting conditions of operation for the primary which senses the conditions for which isolation is l

system isolation fanction, initiation of thw Core required.

Such instrumentation must be available l

Cooling Systems, Control Bod Block and Standby Gas whenever primary containment integrity is required.

l Treatment Systems. The objectives of the specifica-l tions are to assure the effectiveness of the protec-The instrumentation which initiates primary system tive instrumsstatloa when

required, aven during isolation is commected in a dual bus arrangement.

{

periods when portions of such systems are out of j

service for malatenance, and to prescribe the trip Ti.e low water level instrumentation, set to trip at I

settings required to assure adequate performance.

177 in, above the top of the active fuel, closes all Wteen accessary, one chamael may be mada inopeaable isolation valves except those la Group 1.

Details of for brief intervals to conduct required functional valve grouping and reqi.i r ed closing times are given tests and calibrations.

in Specification 3.7.

For valves which isolate at tt.is level, this trip setting is adequate to prevent Some of the settings 4 the lastrumentation that uncovering the core la the case of at break in the initiate or control cose sed costalament cooling have largest time assuelag a 60 sec. valve closing time, tolerances esplicitly str.ted where the high and low Mequired c',oslag times are less than this, values are both critical and.v.ay have a substantial effect os safety. The att points of other instrumen-The low-low reactor water level instrumentation is ration, where only the hi.ph or low end of the setting set to trip when reactor water level is 126.5 in.

above the top of active fuel.

This trip Amesmtment No. p % 119 l

.__..m..

.___m s

i

- i JAFMPP j

l TS.8LE 3.2-1 4

INSTRUMENTATIR Tr1ATJMiTLATES_l'RIMARLCONTalPMD8T_. ISO ( ATION i

Minimum Nimmber of Total Number of Instrument Operable Instrument Chamaels Channels Provided by Design Action spet_TriESystenE)

Imatnennat Trialtynl_Settino fot_hth_.Itie_ Systems (2) 2 (6)

Beactor Low hter 2177 in, above TAF 4 Inst. Channels A

Level 1

Beactor Nigh Pressure < 75 psig 2 Inst. Chamaels D

i (Shetdoma Cooling Isolation) 2 Beactor Zaw-Low-Low 218 in. above TAF 4 Inst. Channels A

=ter teeen 1

2 (6)

Migh Drywell Pressure < 2.7 psig 4 Inst. Channels A

1 2

Migh Radiation b le I3aNormalRated 4 Inst. Channels R

Steam Line Tuseel Full Power Background (9) 2 Low Pressure h in 2825psig(7) 4 Inst. Channels a

Steam Line 2

Nigh Flow m in Steam I14 h of Rated Steam 4 Inst. Channels a

Line Flow 2

h im Steam Line Leak (40*F above man 4 Inst. Channels 8

Detect on High ambient i

Temperature 3

Beactor Cleanup Sys-140*r above maa 6 Inst.. Channels C

tem Equapment Area ambient Nigh Temperature 2

Low Condenser vacuum 18" Hg. Vac (4) 4 Inst. Channels B

Closes MSIV's Amc.iment p-a.

Lg, W. 4e. tg. 9e, spa, 119 ts4

~.. - -

.. ~

s s.

JAFMPP TABLE _L 2-2 INSTRUMEHIAT10tLTHAT_1MLTIATES DR_CONTROLSJHILCORE_M'LCONIAIMMENT CQ0L1NG_ SYSTEMS Minimum No.

Total of Operable Number of Instru-Instrument meat Chamaels Pro-Ites Chamaels Per videa by Design for

_15g.

Trip System (1)

Trin F - tion Jtipleye] Syttima Both Trio Systems Regnerks 1

2 Reactor Low-h 2_126.5 In. above TAF 4 HPCI & RCIC Initiates HPCI, Nater Imvel Inst. Chaamels BCIC & SGTS.

2 2

Reactor Iow *m-

}_18 In. eLove TAF 4 Core Spray & RNR Initiates Core Spray, 14w Mater Level Instrument Chamaels LPCI, and Emergency Diesel Generators.

4 ADS Instrument Initiates ADS in conjunc-Chamaels tion with confirmatory low level, 120 second time delay and LPCI or Core Spray pump discharge pressure laterlock if not inhibited by ADS override switches.

3 2

Reactor Migh Watsr

<222.5 in above TAF 2 Inst. Channels Trips HPCI Turbine and Level closes RCIC steam line isolation valve.

4 1

Reactor Low Level 2_0 in. above TAF 2 Inst. Chamaels Prevents inadvertent (inside shroud) operatica of contain-mest spray during accident condition.

Amena. cat No. 14, % ed, 54 119 a

- _ _ - _ ~ _ _ -. - _. _ - _ -. - _ _ _ _ =

s JAFMPP TABLE 3.2-2 (cont *d)

OR CONTROLS THE CORE AND CONTAIWHENT COOL 1pC SYSTEMS Minimum No.

Total of Operable Number of Instru-Instrument ment Channels Pro-Item Channels Per vided by Design for so.

Trly System (1)

Trip Function Trip Leval Settina Both Trip vstems Romerks 5

2 Containment Nigh 1< p42.7 psig 4 Inst. Channels Prevents is.edvertent Pressure operation of containment spray during accliwt condition.

6 1

Confirmatory Low

[I77 in. above TAF 2 Inst. Channels ADS Permissive in Level conjunction with Reactor Low-Low-Low Water Level.

7 2

Migh Drywell

[2.7psig MPCI Inst. Channels Initiates Core Spray Pressure LPC1, HPCI and SCTS.

O 2

Beactor Low Pres-1450psig 4 Inst. Channels Permissive for opening sure Core Spray and LPCI Admission valves.

l Amesht No. 14. M. FI. 74. 119 61 l

.=

e TABI A.226 SURYEILIANCE_ INSTRUMENTATION Mlaimuss 350.

of Operable No. of Chaamels Instrumment Type Indication Provided Chamaala rmatrunsat and Ranee by DeBlan kclan morrow Range Beactor Level Indicator (13) (2)

(Isote 3) 164.5 to 224.5 is. above TAF 2

marrow Range Recorder 3

si Reactor Level 161.5 to 224.5 is, above TAF (note 4) l Mide Racge 1

Reactor Level Indicator (2)

(Note 14) 14.5 to 224.5 in above TAF 2

j Wide Range Indicator-Recorder Reactor Level it.5 to 224.5 in. above TAF (Note 15) 1 Fuel Zone Isdicetor (2)

Reactor Level 15C in. below to 200 la.

(alote 16) above. TAF 2

Fuel Zone 1sdicator-Recorder 1

Reactor Level 150 in. below to 200 in.

(Note 17) above TAF Reactor Pressure Indicatar (Note 5) 0-1200 psig 2

Reactor Pressure Recorder 5

(1) (2)

(alote 6) 0-1200 psig j

Ame n.1=e n t. No. V, $s,

4. W, p4 119 7 t, i

--vv,w e--

,-er-,,,

,--,-,m e-

s

.~

TADLE_3 J-ft (Coat *d)

SURVEILLAMCE_1MSIRUMIMIATIO!I Minimum aso, et Operable slo. of Chamaels Instramment Type Indication Provided Cheneels I==tr - at mad 3 sage by Design action _

Drymell Pressure (Narrow Range)

(Barrow Range) fadicator secorder 10 - 19 psia 1

Drywell Pressure (Wide Range) 2 (2l IMicator Recorder 0 - 100 psia Drywell Temperature Indicator 10 - 250*F 2

(

(1) (2)

Drywell Temperature Recorder 50 - 350*F Suppression Chant,er Xadicator Teec rature 50 - 250

• F 2

4 (1) (2)

Simppresslos Ch = hr Recorder Temwrature 50 - 350*F j

Amesmtmenit eso. W. 6f, M, 119 7ta

-M -

__.m__.

_.m

.____m..

't 4

6 3QZEE N A3E2 3.2-6 (C9EI15 EDI

14. One (1) indicator from reactor wida range level in.sPr w at chamael A.

15. One (1) indicater-recorder from reactor wide r w level instrument chamael s.

16. One (1) indicator free reactor fine some level Lastrummet chanael A.

17. Ge= (1) indicater-recorder from reactor fuel mona lawel instrument ch==-1 m j

4 l

l nme u. lis l

764 1

i l

[

4 r

=

JAFMPP TABt.E 3.2-7 l

lustra 8TATION THAT 15ITI ATES RECIRCUL ATION PUNP TRIP l

Total Muer,Ser of Instrument i

Cialer g Number of I

Channels Provided by Operable Instrument l

Channels per trip Design for Both Systes (1)

Init runeet Trip Level Setting Channels Action 1

Beactor High Pressure

[1120 prig 4

(2) 1 Beector Leer-Leer 1126.5 in above TAF 4

(2)

Water Level l

Motes for Table 3.2-F I.

Whenever the reactor is in the run mode, there shall be one operable trip systen f or each parameter for each operating recirculation pump.

From and after the time it is found that this cannot "we met, the indicated action shall be taken.

Reduce power and f ace the Mode Selector Switch in a Mode other

han the Run Mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment No. 61. As, 119 11

-s _

.