ML20214K354

Supplemental Application for Amends to Licenses NPF-9 & NPF-17,reassessing Specs & Expanding Bases Per Generic Ltr 83-37 & Proposing Limiting Condition for Operation & Surveillance for Reactor Vessel Head Vent Sys

ML20214K354
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/20/1987
From:	Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20214K355	List: ML20214K354 ML20214K380
References
GL-83-37, TAC-55821, TAC-55822, NUDOCS 8705280414
Download: ML20214K354 (6)

Text

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W DUKE POWER GOMPANY P.O. nox 33189 CHARLOTrE, N.C. 28242 HAL B. TUCKER """

,,,,,, ,,,, 004) amaos secs. man rannocesom May 20,1987 U.S. Nuclear Regulatory Commission (DohiIssmRCondol.Deskiz,3 Washington, D.C. 20555

Subject:

McGuire Nuclear Station Docket Nos. 50-369, 50-370 Proposed Technical Specification Revision Supplement to Proposal Dated September 6,1984 Gentlemen:

By letter dated September 6,1984 Duke proposed a technical specification change in response to NRC Generic Letter 83-37 and NRC letter dated August 3, 1984. The proposed specification was based on the model provided by GL 83-37 with the exception that the requirement to verify the flowpath was not included. Sub-sequently, discussions have taken place between Duke and the NRC and this sup-plement to the previous submittal has been prepared.' This supplement:

a.

Re-assesses the existing McGuire specifications to the model provided by GL 83-37,

b. Proposes an LCO and surveillance for the Reactor Vessel Head Vent System-which includes verification of flow through the vent path, and

c. Expands the Bases that had been provided in GL 83-37.

Attachment 1 is provided for convenience and contains the existing McGuire Spec-ifications 3/4.4.4 Relief Valves and 3/4.4 Overpressure Protection System and the previous proposal for Specification 3/4.4.11. Attachment 2 provides the Technical Justification and Significant Hazards Consideration for this supplemental request.

Attachments 3 and 4 provide the proposed Technical Specification revision and proposed Bases revision.

Duke requests NRC approval of this proposed technical specification revision, which supplements that which was previously provided by my letter dated Sep-tember 6, 1984. Duke also requests that, when approved, this amendment become sffective during the next cold shutdown that starts subsequent to the issuance date, rather than effective immediately as is normally the case. This is because cperability of the Reactor Vessel Head Vent System is determined by surveillance performed once per 18 months during cold shutdown or refueling. Accordingly, '

cperability of this system should only be required following the acceptable 03 0

performance of the specified surveillance which can only be done during cold L shutdown. Should the amendment be issued and immediately effective while one or dg 1

8705280414 870520 PDR ADOCK 05000369 P PDR.

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. Document Control Desk May 20, 1987 Page 2 1

both McGuire units are operating, operability of the Reactor Vessel Head Vent System could be questioned as the specified surveillance had not been performed.

This proposal supplements a previous submittal, as such no additional application fees are required.

Very truly yours, l

$$/W_

Hal B. Tucker RLG/200/jgm Attachments j xc: Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission - Region II j 101 Marietta Street, NW, Suite 2900

i Atlanta, Georgia 30323 W.T. Orders NRC Resident Inspector McGuire Nuclear Station Darl Hood, Project Manager 2

Division of Licensing l Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ,

4 Washington, D.C. 20555

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ATTACHMENT 1A

$ EXISTING McGUIRE TECHNICAL SPECIFICATIONS RELATED TO RELIEF VALVES 3/4.4.4 RELIEF VALVES 3/4.4.9.3 OVERPRESSURE PROTECTION SYSTEMS i

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. REACTOR COOLANT SYSTEM

! 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION l 3.4.4 All power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

1 APPLICABILITY: MODES 1, 2, and 3.

ACTION:

! a. Witn one or more PORV(s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore j the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in i 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 COLD SHUTDOWN 3 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

k b. With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either t

restore the block valve (s) to OPERABLE status or close the block i valve (s) and remove power from the block valve (s) or close the PORV j and remove power from its associated solenoid valve; otherwise, 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 COLD SHUTDOWN l

within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c. The provisions of Specification 3.0.4 are not. applicable.

l SURVEILLANCE REQUIREMENTS i

i 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a. Performance of a CHANNEL CALIBRATION, and i ~

. b. Operating the valve through one complete cycle of full travel.

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4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel

-unless the block valve is closed with power removed in order to meet the requirements of ACTION a. in Specification 3.4.4.

4.4.4.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by:

a. Manually transferring motive and control power from the normal to the emergency power supply, and 2 b. Operating the valves through a complete cycle of full travel.

McGUIRE - UNITS I and 2 3/4 4-10 i

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REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS f

LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following Overpressure Protection Systems shall be OPERABLE:

a. Two power-operated relief valves (PORVs) with a lift setting of less than or equal to 400 psig, or

b. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 4.5 square inches. <

APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is less than or equal to 300 F, MODE 5 and MODE 6 with the reactor vessel head on.

ACTION:

a. With one PORV inoperable, restore the inoperable PORV to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 4.5 square inch vent (s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b. With both PORVs inoperable, depressurize and vent the RCS through at least a 4.5 square inch vent (s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c. In the event either the PORVs or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient, and any corrective action necessary to prevent recurrence.

d. The provisions of Specification 3.0.4 are not applicable.

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l McGUIRE - UNITS 1 and 2 3/4 4-37

REACTOR COOLANT SYSTEM ll. l SURVEILLANCE REQUIREMENTS . .

4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

) a. Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE;

b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and

c. Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure protection.

4.4.9.3.2 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

• when the vent (s) is being used for overpressure protection.

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• Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

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.McGUIRE - UNITS 1 and 2 3/4 4-38

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