ML20207S530
| ML20207S530 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/09/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20207S531 | List: |
| References | |
| DPR-50-A-125 NUDOCS 8703190632 | |
| Download: ML20207S530 (7) | |
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NUCLEAR REGULATORY COMMISSION
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W ASHINGTON, D. C. 20555
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%,.....f t'ETROPOLITAL EDISON COMPANY OFPSEY CENTRAL POWER AND IIGHT COMPANY DENNSY1VANIA ELECTRIC COMPANY GPU NUCLEAR COPPORATIOF DOCKET NO. 50-289 THPEE PILE ISLAND FUCLEAR STAT!0N, UNIT NO.1 AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No.125 License No. DPP-50 1.
The Nuclear Regulatory Com'ission (the Commission) has found that:
A.
The applicetion for amendment by GPL' Nuclear Corporation, et al.
(the licensees) dated November 3, 1986, as supplemented November 10, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; P.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 4
E.
The issuance of this amendment is in accordance with 10 CFP Part 51 of the Commission's regulations and all applicable reouirerents have been satisfied.
8703190632 870309 PDR ADOCK 05000289 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicater'in the attachnent to this license amendment, and paraoraph ?.c.(?) of Facility Operating Licensr No. DPR-50 is hereby amerded to read as follows-Technical Specificatiers The Technical Specifications contained in Appendix A. as revised through Amendment No.125, are hereby incorporated in the license. GPl! Nuclear Corporation stell operate the facility in accordance with the Technical Specifications.
3.
This licerse amendment is effective as of its date of issuance.
F0F THE Nt' CLEAR REGULATORY COPMISSION (s -
l Jo n F. Stolz. Director /
('F Pro,iect Directorate #6
~
ivision of PWR Licerring-B
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9,1987
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ATTACPt'Ft.T TO LICENSF fMFNDMEffi I;0.125 FACILITY OPERATtNA IffERSE NO. OPP-50 00CKET NO. 50-269 Replats the folic *ing pages of the Apperdi). ' A" Technical Specif' cations with the attached pages. The revised pages are identified by Arcrdment nutber and cer:tain vertical lines irdicating the area of change.
Remove Insert 3-26 3-26 3-26a 3-76a 3-T6b 3-26b 3-?6c 3-26c i
s l
r 3.4.1.2.1.
With the Reactor from 250*F to HOT SHUTDOWN and subcritical for at least one (1) hour, two (2) Main Steam Safety Valves per Steam Generator shall be OPERABLE. With less than two (2) Main Steam Safety Valves per Steam Generator OPERABLE, restore at least two (2) MSS Valves to OPERABLE status for each Steam Generator within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
3.4.1.2.2 When the Reactor is above HOT SHUTDOWN, all eighteen (18) tiain Steam Safety Valves shall be OPERABLE or, if any are not OPERABLE, the maximum overpower trip setpoint (see Table 2.3-1) shall be reset as follows:
Maximum Number of Maximum Overpower Safety Valves Disabled on Trip Setpoint Any Steam Generator
(% of Rated Power) 1 92.4 2
79.4 3
66.3 With more than three (3) Main Steam Safety Valves INOPERABLE, restore at least fifteen (15) Main Steam Safety Valves to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
l 3.4.2 Reactor Coolant System temperature 250*F or less.
3.4.2.1 With Reactor Coolant temperature 250*F or less, at least two of the following means for maintaining decay heat removal capability shall be OPERABLE and at least one shall be in operation except as allowed by Specifications 3.4.2.2, 3.4.2.3 and 3.4.2.4 a.
Decay Heat Removal String "A".
b.
Decay Heat Removal String "B".
c.
Reactor Coolant Loop "A", its associated 0TSG, and its associated emergency feedwater flowpath, d.
Reactor Coolant Loop "B", its associated 0TSG, and its associated emergency feedwater flowpath.
I 3.4.2.2 Operation of the means for decay heat removal may be suspended provided the core outlet temperature is maintained below l
saturation temperature.
3.4.2.3 The number of means for decay heat removal required to be operable per 3.4.2.1 may be reduced to one provided that one of the following conditions is satisfied:
a.
The Reactor is in a Refueling Shutdown condition with the Fuel Transfer Canal water level greater than 23 feet above the reactor vessel flange.
3-26 Amendment No. 4, 78, j#,125
F 5
b.' Reactor coolant temperature is less than 140*F with BWST level greater than 44 feet and an associated flow path through the RCS OPERABLE such that core outlet temperature can be maintained subcooled for at least 7 days, c.
Equipment Maintenance on one of the means for decay heat removal ~specified by 3.4.2.1 is required and the equipment outage does not exceed 7 days.
3.4.2.4 Specification 2.4.?.1 does not apply when either of the following conditions exist:
a.
Decay heat generation is less than 188 KW with the RCS full, b.
Decay heat generation is less than 100 KW with the RCS drained down for maintenance.
3.4.2.5 With less than the above required loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.
3-26a I
Amendment No. M,125 I
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F Bases A reactor shutdown following power operation requires removal of core decay heat.
Normal decay heat removal is by the steam generators with the steam dump to the condenser when RCS temperature is above 250*F and by the decay heat renoval system below 250*F. Core decay heat can be continuously dissipated up to 15 percent of full power via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption.
Normally, the capability to return feedwater flow to the steam generators is provided by the main feeduater system.
The main steam safety valves will be able to relieve to atmosphere the total steam flow if necessary.
During hot shutdown or below, only a minimun nunber of Main Steam Safety Valves need to be operable as stated in Technical Specification 3.4.1.2.1 This is to provide Steam Generator overpressure protection during hot shutdown when hot functional testing is being performed.
The minimum number of valves required to be operable allows nargir for testing without jeopardizing plant safety.
Plant specific analysis shows that one Main Steam Safety Valve is sufficient to relieve reactor coolant puno heat and stored energy when the reactor is subcritical by 1*e f.K/K for at least one hour.
One MSS valve is required by the 1968 ASME Boiler and Pressure Vessel Code Section III, Article 9, Paragraph N-910.4 to relieve steam pressure. However, two MSSVs per Steam Generator will provide conservative re du nda ncy.
During power operations, if Main Steam Safety Valves are inoperable, the power level must be reduced, as stated in Technical Specification 3.4.1.2.2 such that the remaining safety valves can prevent overpressure on a turbine trip.
In the unlikely event of complete loss of off-site electrical power to the station, decay heat removal is by either the steam-driven emergency feedwater pump, or two half-sized motor-driven pumps.
Steam discharge is to the atnesphere via the Main Steam Safety Valves and controlled atmospheric relie' valves, and in the case of the turbine driven pump, from the turbine exhaust.(1)
Both motor-driven EFW pumps, or the steam-driven EFW pump are required initially to remove decay heat with one EFW pump eventually suf ficing.
The minimum amount of water in the condensate storage tanks, contained in Technical Specification 3.4.1.1.,
will allow cooldown to 250*F wi th steam being discharged to the atmosphere.
Af ter cooling to 250*F, the decay heat removal system is used to achieve further cooling.
When the RCS is below 250*F, a single DHR string, or single OTSG and its associated emergency feedwater flowpath is sufficient to provide removal of decay heat at all times following the cooldown to 250*F.
The requirement to maintain two OPERABLE means of decay heat removal ensures that a single f ailure does not result in a complete loss of decay heat removal capability.
The requirement to keep a system in operation as necessary to maintain the system subcooled at the core outlet provides the guidance to ensure that steam conditions which could inhibit core cooling do not occur.
l Limited reduction in redundancy is allowed for preventive or corrective maintenance on the primary means for decay heat removal to ensure that
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maintenance necessary to assure the continued reliability of the systems may be accomplished.
i 3-26b Amendme nt No..M7, W,125
As decay heat loads are reduced through decay time or fuel off loading, 0
alternate flow paths will provide adequate cooling for a time sufficient to take compensatory action if the normal means of heat removal is lost.
With the reactor vessel head removed and 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling.
The SWST with level at 44 feet provides an equivalent reservoir available as a heat sink.
Operability of the BWST is to be determined using calculations based on actual plant data or through plant testing at the time the system is to be declared operable. At such times that either of these means is determined to be operable, removal of the redundant or diverse cooling system is permitted.
Following extensive outages or major core off loading, the decay heat generation being renoved from the Reactor Vessel is so low that ambient losses are sufficient to maintain core cooling and no other means of heat removal is required. The system is passive and requires no redundant or diverse backup system.
Decay heat generation is calculated in accordance with ANSI 5.1-1979 to determine when this situation exists.
An unlimited emergency feedwater supply is available from the. river via either of the two motor-driven reactor building emergency cooling water pumps for an indefinite period of time.
The requirements of Technical Specification 3.4.1.1 assure that before the reactor is heated to above 250*F, adequate auxiliary feedwater capability is available.
One turbine driven pump full capacity (920 gpm) and the two half-capacity motor-driven pumps (460 gpm each) are specified. However, only one half-capacity motor-driven pump is necessary to supply auxiliary feedwater flow to the steam generators in the onset of a small break loss-of-coolant accident.
REFERENCES (1) FSAR Section 10.2.1.3 l
l l
l 3-25c Amendment No. 74, M1,125