ML20080K768
| ML20080K768 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/16/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080K771 | List: |
| References | |
| NUDOCS 8309290377 | |
| Download: ML20080K768 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555 S
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DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET N0. 50-334 BEAVER VALLEY POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-66 The Nuclear Regulatory Comission (the Comission) has found that:
1.
N The application for amendment by Duquesne Light Compan A.. Company and Pennsylvania Power Company (the licensees)y, Ohio Edison dated e
April 4,1983 as supplemented by letters dated July 15, and August 19, 1965, 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; 1
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.
0309290377 830916 PDR ADOCK 05000334 P
. 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-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 71, 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.
F R THE NU R-REGULATi)RY COMMISSION
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- ev n ga, Operating Reactor anch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 16, 1983 l
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4 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 71 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET N0. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages l
3/4 5-7 3/4 5-7 3/4 5-8 3/4 5-8 B3/4 5-1 83/4 5-1 B3/4 5-2 B3/4 5 -
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LMEKGthCY CURL COULlhU 5751 015 3/4.5.4 BORON INJECTION SYSTEM BORON INJECTION TANK 2350*F LIMITING CONDITION FOR OPERATION 3.5.4.1.1 The baron injection tank shall be OPERABLE with:
- a.
A minimum contained volume of 900 gallons of borated water,
+* b.
Between 2,000 and 7,700 ppm of boron, and
- c.
A minimum solution temperature of 120*F.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> deviation is permitted to correct the out of specifica-tion ccndition.
+
To permit adequate recirculation and sampling following actions taken to correct the boron concentration, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is allowed for verification of the sample results providing corrective action was taken within the first hour.
With the' Baron Injecti'an Flow Path temperature <l20'F but>65'F, verify Recirculation Flow Path temperature and stagnant piping temperature by local monit6 ring of the ambient air temperature in the 1) Blender Cubicle (722 elevation PAB), and 2) Safeguards Penetration Area A (722 elevation Safeguards building) hourly.
APPLICABILITY:
MODES 1, 2, 3 ACTION:
With the boron injection tank inoperable or <65'F, be in HOT STANDBY and l
borated to a SHUTDOWN MARGIN eqt&;alent to 1% Ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the tank to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.4.1.l' The boron injection tank shall be demonstrated OPERABLE by:
a.
Verifying the water level in the surge tank at least once per 7 days.
~
Verifying the boron concentration of the water in the surge b.
tank at least once per 7 days.
c.
Verifying the water temperature and recirculation flow at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and d.
Verifying that the injection flow path temperature is >120*F (no low temperature alarms or by local monitoring of temperature) each shift.
NOTE:
This specification applicable for N & N-1 loop operation with all Loop stop valves open.
SEAVER VALLEY - VilIT 1 3/4 5-7 Amendment No. 71
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DIENGENCY CORE COOLING SYSTEMS.
HEAT TRACING LIMITING CONDITION FOR OPERATION 3.5.4.2 THIS SPECIFICATION DELETED BEAVER VALLEY - UNIT 1 3/45-8 Anendment No. 71
1 BASES 3/4.5.1 ACCUMULATORS The OPERABILITY of each of the RCS accumulators ensures that a suf ficient volume of borated water vill be immediately forced into the reactor core throogh each of the cold legs in the event the RCS pressure fails below the pressure of the accumulators. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.
The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accuculator injection in the accident analysis are met.
The limit of one hour for operation with an inoperable accumulator minimizes the time exposure of the plant to a LOCA event occurring con-current with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.
3/4.5.2 and 3/4.5.3 <ECCS SUBSYSTEMS The OPERABILITY of two separate and independent ECCS subsy, stems ensures that suf ficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.
Either subsystem operating in conjunction with
- the accumulators is capable of supplying suf ficient core cooling to limit the peak cladding termperatures within acceptable limits for all postulated break sizes ranging form the double ended break of the largest RCS cold leg pipe downward.
In addition, each ECCS subsystem provides long term core cooling capabilit-in the recirculation mode during the accident recovery period.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the accident analysis are met and that subsystem OPERABILITY is maintained._
3/4.5.4 BORON INJECTION SYSTDi The OPERABILITY of the boron injection system as part of the ECCS ensures that suf ficient negative reactivity is injected into the core to limit the l
positive increase in reactivity caused by RCS system cooldown. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rup ture.
BEAVER VALLEY - UNIT 1 B 3/4 5-1 Amendment No. 71
e tritnbtHL t LUKt LUULAHO s t d i tfl3 BASES BORON INJECTION SYSTEM (Continued)
The analysis of a main steam pipe rupture is performed to demonstrate that the following criteria are satisified:
1.-
Assuming a stuck rod cluster control assembly, with or without offsite power, and assuming a single failure in the engineered safeguards, there is no consequential damage to the primary system and the core remains in place and intact.
2.
Energy release to containment from the worst steam pipe break does not cause failure of the containment structure.
3.
Radiation doses are not expected to exceed the guidelines of the 10CFR100.
The limits on injection. tank minimum volume and boron concentration ensure that the assumptions used in the steam line break analysis are met.
Verification of 120*F in the injection flow path as'sures an 8-hour margin to the time at which precipitation of a 7700 ppm boric acid solution would occur without benefit of the building heating system.
Verifying the recirculation flow path and stagnant piping temperatures,
'when the Boron Injection Flow Path temperature is <l20*F and >65'F, by monitoring the ambient air temperatures in the building areas contain-ing that pipfng provides assurance that boron precipitation will not occur.
3/4.5.5 REFUELING WATER STORAGE TANK (RWST)
The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient
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supply of borated water is available for injection by the ECCS fn' the event of a LOCA. The limits on RWST minimum volume and boron concentration ensure l
that 1) sufficient water is available within containment to permit recir-culation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes l
with all control rods inserted except for the most reactive contral assembly.
These assumptions are consistent with the LOCA analysis.
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BEAVER VALLEY - UNIT 1 8 3/4 5-2 Amendment No. 71
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