ML20056D953

Amends 174 & 54 to Licenses DPR-66 & NPF-73,respectively, Adding TS Coverage to Address Failure of More Subsystems than Currently Covered in TS

ML20056D953
Person / Time
Site:	Beaver Valley
Issue date:	08/11/1993
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20056D954	List: ML20056D953 ML20056D970
References
NUDOCS 9308190067
Download: ML20056D953 (14)

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i UNITED STATES :

NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 20555-0001 2

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DUOVESNE LIGHT COMPANY i

OHIO EDISON COMPANY i

PENNSYLVANIA POWER COMPANY' DOCKET N0. 50-334 j

1 BEAVER VALLEY POWER STATION. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 174 i

License No. DPR-66 j

1.

The Nuclear Regulatory Commission (the Commission) has found that:

j A.

The application for amendment by Duquesne Light Company, et.al. (the i

licensee) dated November. 16, 1992, as supplemented. March II, 1993, complies with the standards and requirements of the Atomic Energy-Act of ~1954, as amended. (the Act) and the Commission's rules and

'l regulations set forth'.in 10.CFR Chapter'I; li a

'B.

The facility will' operate in conformity with the' application, j

the provisions of..the Act, and the~ rules and' regulations of th'e

-Commission; C.

There is reannable assuranceL(1) that the activities authorized-by this amendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be-1 conducted:in compliance with the Commission's regulations;

- t 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 l

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.

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- 1 9308190067 930831 i

PDR-ADOCK-05000334 i

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• 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. OPR-66 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.174, 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, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 11, 1993 i

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1

-i ATTACHMENT TO LICENSE AMENDMENT N0.174 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 6-7 3/4 6-7 3/4 6-13 3/4 6-13 3/4 6-14 3/4 6-14 B 3/4 6-2 B 3/4 6-2

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DPR-66 I

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I 10.6

1. RWST TEMPERATURE BETWEEN i

45 Y AND 55 T.

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10.5

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2. MAXIMUM AU.OWABLE CONTA!NMENT

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TEMPERATURE 105 7.

cc 10.4

3. MINIMUM ALLOWABLE CONTAINMENT Q

AIR PARTIALPRESSURE 8.G PSIA.

10.3 g

g x4. MAXIMUM RIVER WATER g

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10.1 x

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UNACCEPTABLE O

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CONTAINMENT i

OPERATION -

TEMPERATURE 2 75 *F W 9 S E

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a 9.7 x

ACCEPTABLE OPERATION

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9.5 2

9.4 3

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9.3 CONTAINMENT TEMPERATURE a 95 *F -

g 9.2 9.1 9.0 8.9 30 35 40 45 50 55 60 65 70 75 80 85 I 90 l

RIVER WATER TEMPERATURE (*F) 88 FIGURE 3.6-1 MAXIMUM ALLOWABLE PRIMARY CONTAINMENT AIR PRESSURE VERSUS RIVER WATER TEMPERATURE i

BEAVER VALLEY - UNIT 1 3/46-7 Amendment No.174 i

'E i

DPR-66 CONTAINMENT SYSTEMS i

CONTAINMENT RECIRCULATION SPRAY SYSTEM t

LIMITING CONDITION FOR-OPERATION t

3.6.2.2 Four separate and independent containment recirculation spray subsystems, each composed of a spray pump, associated heat exchanger and flow path shall be OPERABLE.

APPLICABILITY: MODES 1, 2,

3 and 4.

ACTION:

i a.

With one containment recirculation spray subsystem inoperable,l restore the inoperable subsystem to OPERABLEtstatus within 7 l

days or be in 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 />; restore the inoperable spray system to OPERABLE status within the next 48 l

hours or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

f b.

With two containment recirculation spray subsystems inoperable restore at least one inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 l

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 />.

SURVEILLANCE REQUIREMENTS 4.6.2.2 Each containment recirculation spray subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each accessible s

valve (manual, power-operated, or automatic) in the flow path not locked, sealed or otherwise secured in position, 1

is in its correct' position, b.

When tested pursuant to Specification 4.0.5, manually start each recirculation spray pump and verify. the pump shaft l

rotates;

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c.

At least once per 18 months by verifying that ' on a.

Containment Pressure-High-High signal, the recirculation spray pumps start automatically as follows:

RS-P-1A and RS-P-2B 210 1 5 second delay RS-P-2A and RS-P-1B 225 i 5 second delay BEAVER VALLEY - UNIT 1 3/4 6-13 Amendment No.174 -

DPR-66 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (continued) 1 d.

At least once per 18 months during shutdown, verify that on recirculation

flow, each pump develops the required differential pressure and flow rate as shown below when tested pursuant to Specification 4.0.5:

RS-P-1A and RS-P-1B 2 127 psid at 2 2000 gpm RS-P-2A and RS-P-2B 2 132 psid at 2 2000 gpm e.

At least once per 18 months during shutdown, by:

1.

Cycling each power operated. (excluding automatic) valve in the flow path not testable during plant operation, through at least one complete cycle of full travel.

2.

Verifying that each automatic valve in the flow path actuates to its correct position on a test signal.

3.

Initiating flow through each River Water subsystem and its two associated recirculation spray heat exchangers, and verifying a flow rate of at least 8000 l gpm.

f.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

I BEAVER VALLEY - UNIT 1 3/4 6-14 Amendment No.174 t

DPR-66 CONTAINMENT SYSTEMS BASES 3/4.6.1.4 and 3/4.6.1.5 INTERNAL PRESSURE AND AIR TEMPERATURE The limitations on containment internal pressure and average air temperature as a function of river water temperature ensure that 1) the containment structure is prevented from exceeding its design negative pressure of 8.0 psia, 2) the containment peak pressure does not exceed the design pressure of 45 psig during LOCA conditions, and

3) the containment pressure is returned to subatmospheric conditions following a LOCA.

The containment internal pressure and temperature limits shown as a function of river water temperature describe the operational envelope that will 1) limit the containment peak pressure to less than its design value of 45 psig and 2) ensure the containment internal pressure returns subatmospheric within 60 minutes following a LOCA.

The limits on the parameters of Figure 3.6-1 are consistent with the assumptions of the accident analyses.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment vessel will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 40.0 psig in the event of a LOCA.

The visual and Type A leakage tests are sufficient to demonstrate this capability.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.I and 3/4.6.2.2 CONTAINMENT OUENCH AND RECIRCULATION SPRAY SYSTEMS The OPERABILITY of the containment spray systems ensures that containment depressurization and subsequent return to subatmospheric pressure will occur in the event of a LOCA.

The pressure reduction and resultant termination of containment leakage are consistent with the assumptions used in the accident analyses.

The recirculation spray system consists of four 50 percent capacity subsystems each composed of a spray pump, associated heat exchanger and flow path.

Two of the recirculation spray pumps and motors are located outside containment (RS-P-2A and RS-P-2B) and two pumps and motors are located inside containment (RS-P-1A and RS-P-1B).

The flow path from each pump is piped to an individual 180* recirculation spray header inside containment.

Train "A"

electrical power and river water is supplied to the subsystems containing recirculation spray pumps RS-P-1A and RS-P-2A.

Train "B"

electrical power and river water is supplied to the subsystems containing recirculation spray pumps RS-P-1B and RS-P-2B.

BEAVER VALLEY - UNIT 1 B 3/4 6-2 Amendment No.174 m.

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E UNITED STATES lj NUCLEAR REGULATORY COMMISSION I

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DUOVESNE LIGHT COMPANY OHIO EDIS0N COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 i

BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 54 License No. NPF-73 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duquesne Light Company, et al. (the licensee) dated November 16, 1992, as supplemented March 11, 1993, 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 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 Commission's regulations and all applicable requirements have been satisfied.

i

'O 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. NPF-73 12 hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 54, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION baC7t'A tL Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

-Changes to the Technical Specifications Date of Issuance: August 11, 1993 i

i

ATTACHMENT TO LICENSE AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the;following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert i

3/4 6-12 3/4 6-12 3/4 6-13 3/4'6-13 B 3/4 6-2 B 3/4 6-2 B 3/4 6-3 B 3/4 6-3 i

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p NPF-73 CONTAINMENT SYSTEMS CONTAINMENT RECIRCULATION SPRAY SYSTEM LIMITING CONDITION FOR OPERATION r

3.6.2.2 Four separate and independent containment recirculation spray subsystems, each composed of a spray pump, associated heat exchanger and flow path shall be OPERABLE.

APPLICABILITY:

MODES 1, 2,

3 and 4.

ACTION:

f a.

For subsystems containing recirculation spray pumps 2RSS-P21A or 2RSS-P21B: With one containment recirculation spray subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 />; restore the inoperable spray subsystem to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> l or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

For subsystems containing recirculation spray pumps 2RSS-P21C or 2RSS-P21D:

See action statements in Specification 3.5.2 or 3.5.3.

c.

For subsystems containing recirculation spray pumps 2RSS-P21A and 2RSS-P21C, or 2RSS-P21B and 2RSS-P21D; apply.

Action a above if the inoperable subsystem contains recirculation spray pumps 2RSS-P21A (or B),

and apply Action b above if the inoperable subsystem contains recirculation spray pumps 2RSS-P21C (or D).

SURVEILLANCE REQUIREMENTS 4.6.2.2 Each containment recirculation spray subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position; b.

When tested pursuant to Specification 4.0.5, manually start each recirculation spray pump and verify the pump shaft-rotates; c.

At least once per 18 months by verifying that on a Containment Pressure-High-High signal, each recirculation i

spray pump starts automatically after a 628 15 second delay.

BEAVER VALLEY - UNIT 2 3/4 6-12 Amendment No. 54 i

NPF-73 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (continued) d.

At least once per 18 months, during shutdown, by verifying, that on recirculation flow, each recirculation spray pump develops a differential pressure of 2112 psid at a flow of 2 3500 gpm.

e.

At least once per 18 months during shutdown, by:

1.

Cycling each power operated (excluding automatic) valve in the flow path not testable during plant operation, through at least one complete cycle of full travel.

2.

Verifying that each automatic valve in the flow path actuates to its correct position on a test signal.*

3.

Initiating flow through each Service Water subsystem and its two associated recirculation spray heat exchangers, and verifying a flow rate of at least 11,000 gpm.

f.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

• The specified 18-month surveillance interval during the first fuel cycle may be extended to coincide with completion of the first refueling outage.

BEAVER VALLEY - UNIT 2 3/4 6-13 Amendment No. 54

i NPF-73 CONTAINMENT SYSTEMS BASES 3/4.6.1.4 AND 3/4.6.1.5 INTERNAL PRESSURE AND AIR TEMPERATURE fContinuedi of 45 psig and 2) ensure the containment internal pressure returns subatmospheric within 60 minutes following a LOCA.

Additional operating margin is provided if the containment average air temperature is maintained above 100*F as shown on Figure 3.6-1.

r The limits on the parameters of Figure 3.6-1 are consistent with the assumptions of the accident analyses.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment vessel will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 44.7 psig in the event of a LOCA.

The visual and Type A leakage tests are sufficient to demonstrate this capability.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS f

3/4.6.2.I and 3/4.6.2.2 CONTAINMENT OUENCH AND RECIRCULATION SPRAY SYSTEMS The OPERABILITY of the containment spray systems ensures that containment depressurization and subsequent return to subatmospheric pressure will occur in the event of a LOCA.

The pressure reduction and resultant termination of containment leakage are consistent with the assumptions used in the accident analyses.

The recirculation spray system consists of four 50 percent capacity subsystems each composed of a spray pump, associated heat exchanger and flow path.

All recirculation spray pumps and motors are located outside containment and supply flow to two 360*

recirculation spray ring headers located in containment.

One spray ring is supplied by the "A" train subsystem containing recirculation spray pump 2RSS-P21A and the "B"

train subsystem containing recirculation spray pump 2RSS-P21D with the other spray ring being supplied by the "A" train subsystem containing recirculation spray pump 2RSS-P21C and the "B" train subsystem containing recirculation spray pump 2RSS-P21B.

When the water in the refueling water storage tank has reached a predetermined extreme low level, the C and D subsystems are automatically switched to the cold leg recirculation mode of emergency core cooling system operation.

BEAVER VALLEY - UNIT 2 B 3/4 6-2 Amendment No. 54

NPF-73 CONTAINMENT SYSTEME BASES 3/4.6.2.3 CHEMICAL ADDITION SYSTEM The OPERABILITY of the chemical addition system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA.

The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized.

These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.

3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.

Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for both a LOCA and major secondary system breaks.

3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.

Either recombiner unit is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water, and 3) corrosion of metals within containment.

These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA."

3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM 3/4.6.5.1 STEAM JET AIR EJECTOR The closure of the manual isolation valves in the suction of the steam jet air ejector ensures that 1) the containment internal pressure may be maintained within its operation limits by the mechanical vacuum pumps and 2) the containment atmosphere is isolated from the outside environment in the event of a LOCA.

These valves are required to be closed for containment isolation.

BEAVER VALLEY - UNIT 2 B 3/4 6-3 Amendment No. 54