ML18012A762

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Amend 71 to License NPF-63,extending Allowed Outage Time for RWST While Performing Surveillance Testing of RCS Pressure Isolation Valves
ML18012A762
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 05/06/1997
From: Reinhart M
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18012A763 List:
References
NPF-63-A-071 NUDOCS 9705080339
Download: ML18012A762 (9)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER 8

LIGHT COMPANY et al.

DOCKET NO. 50-400 SHEARON ARRIS NUCLEAR POWER PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. NPF-63 2.

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

A.

The application for amendment by Carolina Power 5 Light Company, (the licensee),

dated March 14,

1997, complies with the standards and requirements of the Ato'mic 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 defehse 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.

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-63 is hereby amended to read as follows:

9705080339 970506 POR AoaCK 05000400 P

PDR

3.

(2) Technical S ecificat'ons and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix 8, both of which are attached

hereto, as revised through Amendment No. 71, are hereby incorporated into this license.

Carolina Power 8 Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Mark Reinhart, Acting Director Project Directorate II-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:

May 6, 1997

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Pa es 3/4 5-9 B 3/4 5-2 Insert Pa es 3/4 5-9 B 3/4 5-2

EMERGENCY CORE COOi SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK LIMiTING CONDITION FOR OPERATION 3.5.4 The refueling water storage tank (RWST) shall be OPERABLE with:

a.

A minimum contained borated water volume of 436,000 gallons.

which is equivalent to 92K indicated level.

. b.

A boron concentration of between 2400 and 2600 ppm of boron.

c.

, A minimum solution temperature of 40'F, and d.

A maximum solution temperature of 125'F.

APPLICABILITY:

MODES l. 2, 3.

and 4.

ACTION:

With the RWST inoperable, restore the tank to OPERABLE status within 1 hour*

l or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 4.5.4 The RWST shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the contained borated water volume in the tank.

and 2.

, Verifying the boron concentration of the water.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is less than 40'F or greater than 125'F Except that while performing surveillance 4.4.6.2.2.

the tank must be returned to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SHEARON HARRIS - UNIT 1 3/4 5-9 Amendment No.

71

0

EMERGENCY CORE CO NG SYSTEMS BASES ECCS SUBSYSTEMS Continued The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.

Surveillance Requirements for throttle valve position and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA.

Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:

(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses.

and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

3/4.5.4 REFUELING WATER STORAGE TANK The OPERABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection into the core by the ECCS.

This borated water is used as cooling water for the core in the event of a LOCA and provides sufficient negative reactivity to adequately counteract any positive increase in reactivity caused by RCS cooldown.

RCS cooldown can be caused by inadvertant depressurization.

a LOCA.

or a steam line rupture.

The limits on RWST minimum volume and boron concentration assure that:

(1) sufficient water is available within containment to permit recirculation 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 with all shutdown and control rods inserted except for the most reactive control assembly.

These limits are consistent with the assumption of the LOCA and steam line break analyses.

The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a

pH value of between 8,5 and 11.0 for the solution recirculated within containment after a

LOCA.

This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

An RWST allowed outage time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is permitted during performance of Technical Specification surveillance 4.4.6.2.2 with a dedicated attendant stationed at valve 1CT-22 in cmmunication with the Control Room.

The dedicated attendant is to remain within the RWST compartment whenever valve 1CT-22 is open during the surveillance.

The dedicated attendant can manually close valve 1CT-22 within 30 minutes in case of a line break caused by a seismic event.

Due to the piping configuration.

a break in the non-seismic or tion of piping during this surveillance could result in draining the RWST elow the minimum analyzed volume.

SHEARON HARRIS -'NIT 1 B 3/4 5-2 Amendment No.

71