ML20134C533
| ML20134C533 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/27/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20134C536 | List: |
| References | |
| DPR-66-A-201 NUDOCS 9702030158 | |
| Download: ML20134C533 (7) | |
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Jh UNITED STATES
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NUCLEAR REftULATORY COMMISSION 2
WASHINGTON, D.C. 20666 4 001
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j DUOVESNE LIGHT COMPANY OHIO EDIS0N COMPANY i
PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20i License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated September 9, 1996, as supplemented December 20, 1996, 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; B.
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 (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 es.t.on 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 Commission's regulations and all applicable requirements have been satisfied.
9702030158 970127 ADOCKOSOOg4 DR
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4 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:
l (2) Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 201, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the j
Technical Specifications.
I 3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
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l J h h Stolz, Directo7 ect Directorate le2 e
1 D vision of Reactor Projects - i/II Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: January 27, 1997 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 201 i
FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 l
Replace the following pages of the Appendix A, Technical Specifications, with 2
the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 3-18 3/4 3-18 i
3/4 5-8 3/4 5-8 1
i B 3/4 5-3 B 3/4 5-3 B 3/4 5-5 B 3/4 5-5
i i
TABLE 3.3-3 (Continued)
DPR-66 l
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 1
h MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION f
4.
STEAM LINE ISOLATION
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a.
Manual 2/ steam line 1/ steam 2/ operating 1,
2, 3
18 line steam line b.
Automatic Actuation 2
1 2
1, 2,
3 13 Logic j
f l
c.
Containment Pressure 3
2 2
1, 2,
3 14 Intermediate-High-High d.
Low Steamline Pressure 3/ loop 2/ loop any 2/ loop 1,
2, 14 loop any loop 3(1) f e.
High Steam Pressure Rate 3/ loop 2/ loop any 2/ operating 3(2) 14 loop loop
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BEAVER VALLEY - UNIT 1 3/4 3-18 Amendment No. 201
DPR-66 EMERGENCY CORE COOLING SYSTEMS
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j 3/4.5.5 SEAL INJECTION FIDW I
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LIMITING CONDITION FOR OPERATION 3.5.5 Reactor coolant pump seal injection flow shall be less than or equal to 28 gpm with the charging pump discharge pressure greater than or equal to 2397 psig and the seal injection flow control valve full l
i open.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With the seal injection flow not within the limit, adjust manual seal injection throttle valves to give a flow within the limit with the charging pump discharge pressure greater than or equal to 2397 psig and the seal injection flow l
control valve full open 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.5 Verify at least once per 31 days that the valves are adjusted to give a flow within the limit with the charging pump discharge at valvefullopen.Opalto2397psigandthesealinjectionflowcontrol l
greater than or e 1
l l
(1)
Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the Reactor Coolant System pressure stabilizes at greater than or equal to 2210 psig and less than or equal to 2250 psig.
BEAVER VALLEY - UNIT 1 3/4 5-8 Amendment No. 201 1
DPR-66 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.5 SEAL INJECTION FLOW BACKGROUND The function of the seal injection throttle valves during an accident is similar to the function of the Emergency Core Cooling Systems (ECCS) throttle valves in that each restricts flow from the charging pump header to the Reactor Coolant System (RCS).
l The restriction on reactor coolant pump (RCP) seal injection flow limits the amount of ECCS flow that would be diverted from the injection path following an accident.
This limit is based on safety analysis assumptions that are required because RCP seal injection flow is not isolated during SI.
APPLICABLE SAFETY ANALYSES All ECCS subsystems are taken credit for in the large break loss of coolant accident (LOCA) at full power.
The LOCA analysis establishes the minimum flow for the ECCS pumps.
The charging pumps are also credited in the small break LOCA analysis.
This analysis l
establishes the flow and discharge head at the design point for the charging pumps.
The steam generator tube rupture and main steam line break event analyses also credit the charging pumps, but are not limiting in their design.
Reference to these analyses is made in assessing cht,nges to the Seal Injection System for evaluation of their effects in rt:lation to the acceptance limits in these analyses.
This LCO ensures that seal injection flow of less than or equal to 28 gpm, with charging pump discharge pressure greater than or equal to 2397 psig and seal injection flow control valve full open, will be j
sufficient for RCP ceal integrity but limited so that the ECCS trains will be capable of delivering sufficient water to match boiloff rates soon enough to minimize uncovering of the core following a large LOCA.
It also ensures that the charging pumps will deliver sufficient water for a small LOCA and sufficient boron to maintain the core subcritical.
For smaller LOCAs, the charging pumps alone deliver sufficient fluid to overcome the loss and maintain RCS inventory.
BEAVER VALLEY - UNIT 1 B 3/4 5-3 Amendment No.201
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DPR-66 i
EMERGENCY CORE COOLING SYSTEMS j
BASES e
l 3/4.5.5 SEAL INJECTION FIDW (Continued)
ACTIONS g.
With seal injection flow exceeding its limit, the amount of j
charging flow available to the RCS may be reduced.
Under this condition, action must be taken to restore the flow to l
below its limit.
The operator has 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from the time the j
flow is known to be above the limit to correctly position the manual valves and thus be in compliance with the accident i
analysis.
The completion time minimizes the potential l
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exposure of the plant to a LOCA with insufficient injection flow and ensures that seal injection flow is restored to or below its limit.
This time is conservative with respect to the completion times of other ECCS LCOs; it is based on l
operating experience and is sufficient for taking corrective actions by operations personnel.
When the required actions cannot be completed within the required completion time, a controlled shutdown must be initiated.
The plant must be brought to at least MODE 3 j
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 4 within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The allowed completion times are reasonable, based on operating experience and normal cooldown rates, and do not challance plant safety systems or operators.
SURVEILLANCE REOUIREMENTS (SR)
SR 3.5.5.1 Verification every 31 days that the manual seal injection throttle valves are adjusted to give a flow within the limit ensures that proper manual seal injection throttle valve position, and hence, proper seal injection flow, is maintained.
The Frequency of 31 days is based on engineering judgment and is consistent with other ECCS valve Surveillance Frequencies.
The Frequency has proven to be acceptable through operating experience.
As noted, the Surveillance is not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the RCS pressure has stabilized within a i 20 psig range of normal operating pressure.
The RCS pressure requirement is specified since this configuration will produce the required pressure conditions necessary to assure that the manual valves are set-correctly.
The exception is limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to ensure that the Surveillance is timely.
BEAVER VALLEY - UNIT 1 B 3/4 5-5 Amendment No. 201
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