ML20054C005

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Amend 69 to License DPR-59,revising Requirements for Hpis Suction Valve Closure Times.Max Closure Time Revised from 60 Seconds to 80 Seconds
ML20054C005
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/26/1982
From: Vassallo D
Office of Nuclear Reactor Regulation
To:
Power Authority of the State of New York
Shared Package
ML20054C006 List:
References
DPR-59-A-069 NUDOCS 8204190368
Download: ML20054C005 (11)


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UNITED STATES y

NUCLEAR REGULATORY COMMISSION

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WA5HlNGTON. D. C. 20586

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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.69 License No. DPR-59 1.

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

A.

The application for amendment by the Power Authority of the State of New York dated March 9,1982 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regula-tions set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) 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 comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements i

have been satisfied.

f kD[doch60 820326 O0000333 P

PDR

2 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(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

69, 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 Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: March 26.1982

ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET N0. 50-333 Revise Appendix A as follows:

Remove Insert 27 27 27a 43 43 76 76 76a 76a 76b 76b 76c 181 1 81 202 202 l

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JAFNPP 2.2 R_EACTOR C005. ANT SYSTEM 1.2 REACTOR COOf. ANT $YSTDi Arr!.TCABILITY :

ArrLICARTI.1TY:

Applice to trip ecttings of the toetru-Applice to limite on reactor coolant mente and devices which are provided to system preneure.

psevent the reactor coolant system esfety limite from being exceeded.

OBJECTIVE:

't ORIECTIVE:

To define the level of the process To establish a limit below which the variables at which automat ic protective integrity of the steactor Coolant Syerem actton is Spitiated to prevent the safety is not threatened due to en overpressure limits from being suceeded.

ll condition, i

SI KIFICATION:

SI'ECI FIC AT lati 1.

The 1.imiting Safety System setting 1

The reactor coolent system pressure sh.all be specified below:

shall not exceed 1,325 pois at any Line when irradiated fuel le present A.

Reactor coolant high pressure scram f aa the reactor vessel.

sleell be $ 1,045 psis.

5.

Reactor coolant eyeres safety / relief valve nominal sett ings shall be se followet

.l Safety / Relief Valves 2 volves et 1090 pets 2 valves at 1105 sisty 7 valves at 1140 psia l'

The allowatile setswitnt error for each safety /rettet valve shall be e,1 percent.

21 6,/t, pig,69 A coamcot no.

JAFNPP j

TABIE 3.1-1 (cont'd)

REACIOR PICITX'PICN SYS*ITN (SCRAM) IPETRLMENTATION REUJIRENENT s

PCIES CF DBIE 3.1-1 (cont'd)

C.

High Flux IIN D.

Scram Discharge Volune High Invel l

l E.

APIN 15% Power ' Trip 7.

Not required to be operable when primary oxitairrnent integrity is not required.

8.

Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.

9.

'Ihe APIN downscale trip is autanatically bypassed when the IIN Instnrnentation is operable and not high.

10. An APIN will be considered operable if there are at least 2 IPrN inputs per level and at least 11 IPIN inputs of the normal carplanent.
11. See Section 2.1.A.l.
12. '1his equation w.'ll be used in the event of operation with a maximum fraction of limiting power density (MFIPD) greater than the fraction of rated pwer (FRP).

l where:

FRP

= Fraction of rated thermal power (2436 Mit) 1 l

ffIPD

= Maxinun fraction of limiting power density where the limiting Ixwer density is 13.4 KW/ft for 8x8, 8x8R and P8x8R fuel.

'Ihe ratio of FRP to bFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used 6

W

= Icop Recirculation flow in percent of rated (rated is 34.2 x 10 lb/hr)

S

= Scrarn setting in percent of initial

13. 'Ihe Average Power Range )bnitor scram function is varied (Figure 1.1-1) as a function of recirculation loop flow (W). 'Ihe trip setting of this function nust be maintained in accordance with Specification 2.1.A.l.c.

Ama.inent No. pf, s#,5(,fyr,69 43 A

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TABIE 3.2-6 SURVEILIANCE ItSIRT4E2n7,TICN Minimum Ib.

of Operable No. of Channels Instrument Type Indication Provided Channels Instrument and Range by Design Action Reactor Irvel Indicator (13) (2)

(tbte 3) 0 - +60 (164.5 to 224.5 in.

2 above the top of active fuel) 5 i

Reactor level Recorder (tbte 4) 0 - +60 I

(164.5 to 224.5 in. above the top of active fuel) 1 Reactor Level Indicator 2

(2)

-150 - +60 (14.5 to 224.5 in.

above the top of active fuel)

Reactor Pressure Indicator (tbte 5) 0-1200 psig 2

Reactor Pressure Pecorder (Note 6) 0-1200 psig Drywell Pressure (Narrow Range)

(Narrow Range)

Indicator Recorder 10 - 19 psia Drywell Pressure (Wide Range)

(Wide Range)

Indicator Recorder 0 - 100 psia Nmrv5, + m. # off, W, 67', 69 76

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TABLE 3.2-6 f

SURVEILLANCE INSTRUMENTATION Minimum No.

I of Operable No. of Channels Instrument Type Indication Provided Channels Instrument and Range by Design Action 4

(Suppression Chamber Indicator

)

(Water Level Recorder

)

( (Wide Range)

-72 to + 72 inches) 1

(

)

2 (2)

(Suppression Chamber Indicator

)

(Water Level Recorder

)

j

( (Narrow Range)

-6 to +6 inches

)

1 N/A Control Rod Indicator 1

(7)

[

Position Indication Position 00 to 48 2

Source Range Indicator 4

(8)

Monitors Recorder 6

1 to 10 cps 3

Intermediate Indicator 8

(8) (9)

Range Monitor Recorder 10-4 to 40% Rated Power 2

Average Power Indicator 6

(8) (9)

Range Monitors Recorder 0-12Ct Rated Power 1

Drywell-Suppression Recorder 2

(2)

Chamber Differential O to 5 psi Pressure Computer O to 5 psi 1

Safety / Relief Valve Indicator 2

(12) (11)

Position Indicator Open/ Closed (Note 10)

NOTES FOR TABLE 3.2-6 1.

From and after the date that the minimum number of operable instrument channels is one less than the minimum number specified for each parameter, continued operation is permissible during the succeeding 30 days unless the minimum number specified is made operable sooner.

Amendment Hog 69 76 b 2w /h.

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NOTES FOR TABLE 3.2-6 (CONTINUED) 2.

In the event that all indications of this parameter is disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.

3.

Three (3) indicators from level instrument channel A, B,

& C.

Channel A or B are utilized for feedwater control, reactor water high and low level alarms, recircula tion pump runback. High level trip of main turbine and feedwater pump turbine utilizes channel A, B,

& C.

4.

One (1) recorder utilized the same level instrument channel as selected for feedwater control.

5.

Three (3) indicators from reactor pressure instrument channel A, B,

& C. Channel A or B are i

utilized for feedwater control and reactor pressure high alarm.

6.

One (1) recorder. Utilizes the same reactor pressure instrument channel as selected for feedwater control.

t 7.

The position of each of the 137 control rods is monitored by the Rod Position Information 4

r System. For control rods in which the position is unknown, refer to Paragraph 3.3.A.

8.

Neutroa monitoring operability requirements are specified by Table 3.1-1 and Paragraph 3.3.B.4.

9.

A minimum of 3 IRM or 2 APRM channels respectively must be operable (or tripped) in each safety system.

10.

Each Safety Relief Valve is equipped with two acoustical detectors of which one is in service and a backup thermocouple detector.

11.

From and after the date that none of the acoustical detectors is operable but the thermocouple is operable, continued operation is permissible until the next outage in which a primary containment. entry is made. Both acoustical detectors shall be made operable prior to restart.

12.

In the event that both primary and secondary indications of this parameter for any one valve are disabled and neither indication can be restored in forty-eight (48) hours, an orderly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in twelve (12) hours and in a Cold Shutdown within the next twenty-four (24) hours.

13.

From and after the date that the minimum number of operabic instrument channels is one j

less than the minimum number specified for each parameter, continued operation is permissable during the succeeding 7 days unless the minimum number specified is made operable sooner.

Amendment No.

46, p1, 69 76 c

JAFNPP 3.7 (cont'd) 4.7 (cont'd) 9.

Primary Containment Atmosphere 9.

Primary Contairinent Atnesphere Fbnitoring Instnznents Fbnitoring Instrunents a.

Primary contairrnent atnos-a.

Instrumentation shall be phere shall be continuously functionally tested and monitored for hydrogen and calibrated as specified in oxygen when the contairinent Table 4.7-1.

integrity is required.

B. Standby Gas Treatment Systs B.

Standby Gas Treatment System 1.

Except as specified in 3.7.B.2 1.

Standby Gas Treatment Syst m below, both circuits of the surveillance shall be perfor d Standby Gas Treatment System shall as indicated below:

be operable at all times when secondary containment integrity

a. At least once per operating is required.

cycle, it shall be demonstrated that:

(l.) Pressure drop across the cmbined high-efficiency and charcoal filters is less than 5.7 in of water at 6,000 scfm and (2.) Each 39 KW heater shall dissipate greater than 29KW of electric power as calcu-lated by the following ex-pression:

P = h EI hhere: P = Dissipated Electrical Amendnent No. )d, )fI, g,pf, 69 Power; E = Measured line-to-line 181 voltage in volts (IDE); I = Aver-age measured phase current in amperes (Ees)

JAPgey

~

TABIE 3.T-1 (CXrit'd)

PN PIPELIFE PFN'rWLT!!C PRIMAPY Ctr*T?Decrr (parters in puentheses are keyed to rusters cm folicwiry pars: signal artes are listal ori followirq pers) fuer incatacn Pwer Closirq Dryell Valve Type to Qwn PPf. to to Close Isolaticm Tame ternal Itenarks and Line Isolatert twetraticm (6)

(5) (6)

Grnp trywell (5) (6)

Signal (7)

Status Dicroticma HPCI - Turbine X-214 Orck FW Flow B

OJtside Prtress kv. Flcas tbt applicable Qen Closes on Rev. Flow or Dd.sust I m exhaust pressure HFCI - lurt> ire X-214 Orci fW Flcw B

Outside Prtress RPv. Flcw tbt agplicable Qum D$ dust j

HTC! Pttp Sucticm X-226 PO Gats-Ec B

Outside De L, R1 tot a[plicable Cloesd IGCI Pirp Suction X-226 PO Gate De B

Outside DC L,5N tbt a[plicable Closed HTCI - Ptrp X-98 to Cate It B

O2tside De IN tbt agplicable Closed Discharge HTCI - Turbire X-222 Sttp Occk IV Flcw a

Outside Pro &ss Rey, ficw ta>t applicable Closed D$aust Drain

'I HTCI - Mininsn i,-210B Owrk IW Flow B

Ourside Process feev flow tbt arplicable Cloard Ptrp Flow HTCI - Minian X-210B Pb Glche De B

Outside Dc 1,, fM 10 Sac Closed Pttp Flow

[RWiF21 A1MEPICRIC MPrITOL Ato Sf3NIGS Servim Air to X-21 Orck Process C

Inside Process Rev. flow tht a[plicable Closed trywl1 Service Aar to X-21 Hand Gate Hand C

Outside Hand tbt aEplicable Closed trywl1 Instrtment Air to X-22 Orck Process C

Inside Pro & ss th=v. flow tbt A[plicable Qen Drywll Instrwent Air to X-22 Hard Gate Hard C

Outside Harri tbt agplicable Qam z

Drywll Breathirq Air to X-61 Orck Pro su C

Inside Process Iter. ficw Not agplicable Cloned trywell Breathirq Air to X-61 Har:2 Cate Hard C

02tside Hand tbt agplicable Clcand Drywell Drywll Purge Inlet X-25,X-71 AO Ebtterfly Air /Ac B

Oitside Spriry F,A,2.fM 5 Sec Closed Drywell Purge Inlet X-25,X-71 AO Butterfly Air /Ac B

O2tside Spring F A,2,1M 5 Sec Closed 1 Nin X-26A,8 Jo Butterfly Air /Ac B

Outside Sprirn F,A,2,1N 5 Sec Cloerd h>stit tb. 48, 48 Amendment No. AS, AS, 69 202 l C7 l

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