ML20138P514
| ML20138P514 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/29/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20138P518 | List: |
| References | |
| DPR-59-A-095, GL-84-015 NUDOCS 8511070210 | |
| Download: ML20138P514 (10) | |
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UNITED STATES
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~,j NUCLEAR REGULATORY COMMISSION e t WASHINGTON D. C. 20555 5
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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. 95 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 (the licensee) dated April 26, 1985, 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 CFR 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 can be conducted without endangering the 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 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 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(2) of Facility Operating License No.
DPR-59 is hereby amended to read as follows:
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I (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, 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: October 29, 1985 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
2 Pages 114 115 115a 116 117 126 217 Y
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JAFNPP 3.5 (cont'd) 4.5 (cont'd) 2.
From and after the date that 2.
When it is determined that one of the Core Spray Systems one is made or found inoperable for Core Spray System is inoperable, any reason, continued reactor the operable Core Spray System, and the LPCI System, shall be demon-operation is permissible during the succeeding 7 days unless strated to be operable immediately.
g:
the system is made operable The remaining Core Spray System shall e
earlier, provided that during be demonstrated to be operable daily thereafter, i
the 7 days all active components of the other Core Spray System l
and the LPCI System shall be operable.
i 3.
The LPCI mode of the RHR System 3.
shall be operable whenever ir-LPCI System testing shall be as i
radiated fuel is in the reactor specified in 4.5.A.la, b,
c, d,
and prior to reactor startup f and g except that three RHR pumps shall deliver at least 23.100 gpm from a cold condition, except i
as specified below.
against a system head corresponding to a reactor vessel pressure of 20
- psig, t
a.
From the time that one a.
When it is determined that of the RHR pumps is made or found to be inoperable one of the RHR pumps is for any reason, continued inoperable, the remaining reactor operation is per-active components of the LPCI, containment spray missible during the j
succeeding 7 days unless subsystem and both Core Spray l
the pump is made operable Systems required for operation l i
earlier provided that dur-shall be demonstrated to be ing such 7 days the remain-operable immediately, and the ing active components of remaining RHR pumps shall be I
the LPCI, containment demonstrated to be operable I
daily thereafter.
spray mode, and all activh components of both Core Spray Systems are Operable.
1 l
1i Amendment No. )4F. )Hf 95, 114 4
1 1
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JAFNPP P
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j 3.5 (Cont'd) 4.5 (Cont'd) h.
From the time that the LPCI mode is made or b.
When it is determined that the LPCI mode is found to be inoperable for any reason, inoperable, both Core Spray Systems, and the continued reactor operation is permissible containment spray subsystem shall be demonstrated to during the succeeding 7 days unless the LPCI be operable immediately and daily thereafter.
mode is made operable earlier provided that i
during these 7 days all active components of both Core Spray Systems and the containment l
spray subsystem (including two RHR pumps) shall be operable.
c.
When the reactor water temperature is greater c.
The power source disconnect and chain lock to motor than 21L*F, the motor operator for the RHR operated RHR cross-tie valve, and lock on manually cross-tie valve (MOV20) shall be maintained operated gate valve shall be inspected once each disconnected from its electric power source.
operating cycle to verify that both valves are It shall be maintained chain-locked in the closed and locked.
closed position. The manually operated gate valve (10-RNR-09)'in the cross-tie line, in seri.es with the motor operated valve, shall be maintained locked in the closed position.
4.a.
The reactor shall not be started up with the RHR System supplying cooling to the fuel pool.
b.
The RHR System shall not supply cooling to the spent fuel pool when the reactor coolant temperature is above 212*F.
- e Amendment No.
p6 95 115 j
i 4
JAFNPP 3.5 (Cont'd) 4.5 (Cont'd) 5.
All recirculation pump discharge valves and 5.
All recirculation pump discharge and bypass valves bypass valves shall be operable prior to shall be tested for operability any time the reactor reactor startup (or closed if permitted is in the cold condition exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if elsewhere in these specifications).
operability tests have not been performed during the preceding 31 days.
l 6
If the requirements of 3.5.A cannot be met, the reactor shall be placed in the cold conditinn within 24 hrs.
l l
B.
CONTAINMENT COOLING SUBSYSTEM NODE (OF B.
CONTAINMENT COOLING SUBSYSTEM MODE (OF THE RHR SYSTEM)
THE RHR SYSTEM)
I.
Both subsystems of the containment cooling 1.
Subsystems of the containment cooling mode are mode, each including two RHR, one ESW pump and
- tested in conjunction with the test performed on the two RHRSW pumps shall be operable whenever LPCI System and given in 4.5.A.1.a. b, e, and d.
i there is irradiated fuel in the reactor vessel, Residual heat removal service water pumps, each loop prior to startup from a cc,ld condition, and consisting of two pumps operating in parallel, will i
reactor coolant temperature > 212*F except as he included in testing, supplying 8,000 gps. The specified below:
Emergency Service Water System, each loop of which consistr. of a single operating emergency service watet pump of 3,700 gpm will be tested in accordance with Section ~.11D.
I
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During each five-year period, an air test shall be performed on the containment spray headers and nozzles.
2.
Continued reactor operation is permissible for 2,
When it is determined that one RHR pump and/or one 30 days with one spray loop inoperable and with RHRSW pump of the components required in 3.5.B.1 reactor water temperature greater than 212*F.
above are inoperable, the remaining redundant active components of the containment cooling mode j
subsystems shall be demonstrated to be operable immediately and daily thereafter.
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.l Amendment No.,)d' 95 115a b
I
JAFNPP 1.5 (Cont'd) 4.;
(Cont'd) 3.
Should one RHR pump and/or one R!lRSW purp of 3.
When one containment cooling subsystem loop becomes the components required in 3.5.B.1 above be inoperable, the operable loop shall be demonstrated made or found inoperable, continued reactor to be operable immediately and daily thereafter.
operation is permissible only during the succeeding 30 days provided that during such 30 days all remaining active components of the centainment cooling mode are operable.
4 Should one of the containment cooling subsystems become inoperable, continued reactor operation is Permissible for a period not to exceed 7 days, unless such subsystem is sooner made operable provioed that during such 7 days all active components of the other containment cooling sut:y:::= are operable.
5.
If the requirements of 3.5.B cannot be met, the reactor shall be placed in a cold condition within 24 hr.
6.
Low power physics testing and reactor operator training shall be permitted with reactor coolant temperature < 212*F with an inoperable component (s) as specified in 3.5.B above.
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Amendment No. )( 95 116
J,AFNPP 3.5 (cont'd) 4.5 (cont'd)
DELETED C.
HIGH PRESSURE COOLANT INJECTION C.
HIGH PRESSURE COOLANT INJECTION (HPCI SYSTEM)
(HPCI SYSTEM)
Surveillance of HPCI System shall be performed as follows provided reactor steam supply is available.
If steam is not available at the time the surveillance test is scheduled to be performed, the test shall be performed within 10 days of continuous operation from the time steam becomes available.
1.
The HPCI System shall be operable 1.
HPCI System testing shall be as specified whenever the reactor pressure is in 4.5.A.l.a, b, c, d, f, and g except greater _than 150 psig and irradiated that the HPCI pump shall deliver at least 1
fuel is in the reactor vessel and 4,250 gpm against a system head correspon-prior to reactor startup from a ding to a reactor vessel pressure of 1120 i
cold condition, except as specified psig to 150 psig.
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below:
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Amendment No. Jmf 95 7
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JAFNPP 305 BASES (cont'd) l the RHR System in conjunction with given in Reference 8 provides a the Core Spray System provides quantitative method to estimate adequate cooling for break areas of allowable repair times, the lack of approximately 0.2 sq. ft. up to and operating data to support the including the double-ended reactor analytical approach prevents J
recirculation line break without complete acceptance of this method j
assistance from the high pressure at this time.
Therefore. the times Emergency Core Cooling Systems.
stated in the specific items were l
established with due regard to l
The allowable repair times are judgement.
j established so that the average risk l
rate for repair would be no greater Should one Core Spray System become j
than the basic risk rate.
The inoperable, the remaining Core Spray j
method and concept are described in and the entire LPCI System are l
Reference 8.
Using the'results available should the need for core developed in this reference, the cooling arise.
To assure that the i,
repair period is found to be less remaining Core Spray and LPCI than 1/2 the test interval.
This Systems are available. they are assumes that the Core Spray and LPCI demonstrated to be operable Systems constitute a 1-out-of-2 immediately.
This demonstration I
systems; however, the combined effect includes a manual initiation of the of the two systems to limit excessive pumps and associated valves.
l clad temperatures must also be con-Based on judgements of the reli-sidered.
The test interval specified ability of the remaining systems.
in Specification 4.5 was 3 months, i.e.,
the Core Spray and LPCI. a Therefore, an allowable repair period seven-day repair period was obtained.
I.'
which maintains the basic risk l
considering single failures should be Should the loss of one RHR pump less than 30 days, and this speci-occur, a nearly full complement of f
fication is within this period.
core and containment cooling i
For multiple failures, a shorter equipment are available.
Three RHR interval is specified and to improve pumps in conjunction with the Core i
the assurance that the remaining spray System will perform the core i
I systems will function, a daily test is cooling function.
Because of the j
' called for.
Although it is availability of the majority of the recognized that the information l
Amendment No.
95 i
126 l
.1APf1Pp 3.9 (cont'd) 3.
From and af ter the time that one 3.
The emergency diesel generator of the Emergency Diesel Generator system instrumentation shall be Systems is made or found to be checked during the monthly generator inoperable, continued reactor test.
operation is permissible for a period not to exceed 7 days provided that the two incoming power sources are available and connected to the emergency bus associated with the 5
inoperable Emergency Diesel Generator System and that the remaining Diesel 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 one or both diesel generator systems are made operable sooner.
4.
When both Emergency Diesel Generator 4.
Once each operating cycle, the Systems are made or found to be conditions under which the inoperable, a reactor shutdown Emergency Diesel Generator System shall be initiated within two hours is required will be simulated to and the reactor placed in a cold demonstrate that the pair of diesel condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after generators will start, accelerate, initiation of shutdown.
force parallel, and accept the emergency loads in the prescribed a
sequence.
5.
Once within one hour and at least once per twenty-four hours there-l after while the reactor is being operated in accordance with 1
Specifications 3.9.B.1, 3.9.B.2, and 3.9.B.3, the availability of the operable Emerip ncy liienel GeneraLorn shall be ilenwinst rated i
by mannal nt a rt.i nq and force paralleling where applicable.
l Amnndmont flo. yf 95 4
217