ML19260B258
| ML19260B258 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/23/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19260B259 | List: |
| References | |
| NUDOCS 7912070483 | |
| Download: ML19260B258 (7) | |
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E WASHINGTON, D. C. 20555 BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION, UNIT NO. 1 AMENCMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Boston Edison Company (the licensee) dated January 16, 1976, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Corrnission'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 Conmission; 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 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reouirements have been satisfied.
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. 2.
Accoraingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-35 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 38, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effr tive as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'?<kpW Thomas /k. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications
'Date of Issuance: ?!ovember 23, 1979 1515 100
ATTACHMENT TO LICENSE AMENDMENT NO. 38 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Revise Appendix A as follows:
Remove the following pages and insert identically numbered pages-105
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106 107 115 fD f
LIMITIN3 CONDITIONS FOR OPERATION SURVEILLANCE RE0UIREMENT 3.5.A Core Soray and LPCI Subsystems 4.5.A Core Soray and LPCI Subsystems (Cont'd)
(Cont'd) 4 From and after the date that one 4.
When it is aetermined that one of of tne RHR (LPCI) pumps is made the RHR (LPCI) ourps is inoperable at a time when it is recuired to be or found to be inoperable for any reason, continued reactor opera-operable, the containment cooling tion is pennissible only during subsysten, the remaining active the succeeding thirty days pro-components of the LPCI Subsystem, vided that during such thirty days both core spray systems and the i
the containment cooling subsystem, !
diesel generatres shall be demon-the remaining active components strated to be operable imediately of the LPCI Subsystem, ard all and the operable LPCI pumps daily active components of both cora j
thereafter.
spray subsystems and the diesel generators are operable.
A 5.
From and after the date that the 5.
When it is determined that the LPCI LPCI subsystem is made or found subsystem is inoperable, both core to be inoperable for any reason, spray subsystems, the containmen.t continued reactor operation is i
cooling subsystem and the diesel i
generators required for operation pennissible only during the succeeding seven days unless l
of such components if no external it is sooner made operable, pro-source of power were available shall i
vided that during such seven be demonstrated to be operable immediately and daily thereafter.
days the containment cooling subsystem (' including 2 LPCI pumps) and active components of both core spray subsystems, and the diesel generators required for operation of such components if no external source of power were available shall be operable, j
i 6.
If the requirements of 3.5.t.
cannot be met, an orderly shut-down of the reactor shall be initiated and the reactor shall i
be in the Cold Shutdown Con-dition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i 1515 10k 105
LI"ITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.B Containment Cooling Subsystem 4.5.8 Containment Coolina Subsystem l
1.
Containnent Cooling Subsystem Testing 1.
Except as specified in 3.5.B.2, 3.5.B.3, and 3.5.F.3 below, snall be as follows:
both containment. cooling sub-system loocs shall be operable Item Freauency whenever irradiated fuel is in the reactor vessel and reactor a.
Pump & Valve coolant temperature is greater Operability Once/3 months than 212*F, and prior to i
reactor startup from a Cold b.
Pump Capacity Test After pump Condition.
Each RBCCW pump shall maintentace deliver 1700 gpm and every at 70 ft. TDH.
3 months l
Each SSWS pump shall deliver 2700 gpm at 55 ft. TDH.
c.
Air test on drywe'l Once/5 years and torus headers and nozzles i
i l
f h
l 1
l l
i f
I i
l I
106 1515101s
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.5 Containment Coolino subsystem 4.5.B Centainment Cooline Subsystem (Cont'd)
(Cont'd) 2.
Fron and after the date that one 2.
When one containment cocling sub-containment cooling subsystem syster loop becomes inocerable, loop is made or found to be the operable subsysten loop and inoperable for any reason, con-its associated diesel generator tinued reactor operation is shall be demonstrated to be permissible only during the operable immediataly and the succeeding seven days unless operable containment cooling subsystem loop daily thereafter.
i such subsystem loop is sooner l
made operable, provided that i
the other containment cooling j
subsystem loop, including its I
associated diesel generator, is operable, i
3.
If the requirements of 3.5.B cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j i
i.
C.
HPCI Subsystem l
C.
HPCI Subsystem 1.
The HPCI Subsystem shall be l.
HPCI Subsystem testing shall be operable whenever there is performed as follows:
irradiated fuel in the reactor a.
Simulated Auto-Once/ operating vessel, reactor pressure is greater than 104 psig, and matic Actuation cycle prior to reactor startup from Test a Cold Condition, except as specified in 3.5.C.2 and j
b.
Pump Operability Once/ month 3.5.C.3 below.
Motor Operated Once/ month c.
Valve Operability d.
Flow Rate at Once/3 months 1000 psig e.
Flow Rate at Once/ operating 150 psig cycle 1515 101 107
BASES:
~
3.5.8 Cantainment Coolino Subsystem The containment cooling subsystem for Pilgrim I consists of two independent loops, each of which to be an operable loop requires one LpCI pump, two RBCCW pumps, cnd two SSW pumps to be operable.
There are installed spares for margin above the design conditions. Eac system has the capability to perfom its function; i.e., removing 64 x 10g Btu /hr (Ref. Amendment 18),
i i
even with scae system degradation.
If one loop is out-of-service, reactor operation is permitted for seven days with daily testing of the operable loop and t.ie appropriate diesel generator.
With components or subsystems out-of-service, overall core and containment cooling reliability is maintained by demonstrating the operability of the remaining cooling equipment. The degree of operability to be demonstrated depends on the nature of the reason for the out-of-service equipment. For routine out-of-service periods caused by preventative maintenance, etc., the pump and valve operability checks will be performed to demonstrate operability of the remaining components. However, if a failure, design deficiency, etc., caused the out-of-service period, then the demonstration of operability should be thorough enough to assure that a similar problem does not exist on the remaining components.
For example, if an out-of-service period were caused by failure of a pump to deliver rated capacity, the other pumps of this type might be subjected to a capacity test.
In any event, surveillance procedures, as required by Section 6 of these specifications, detail the required extent of testing.
Since some of the SW and RBCCW pumps are required for normal operation, capacity testing of individual pumps by direct flow measurement is impractical.
The pump capacity test is a comparison of measured pump performance parameters to shop performance tests combined with a comparison to the performance of the previously tested pump. These pumps are rotated during operation and performance testing will be integrated with this or performed during refueling when pumps can be flow testeo individually. Tests during normal operation will be performed by measuring the shutoff head. Then the pump under test will be placed in service and one of the previously operating pumps secured.
Total flow indication for the system vill be compared for the two cases.
Where this is not feasible due to changing system conditions, the pump dis-charge pressure will be measured and its power requirement will be used to establish flow at that pressure.
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