ML18009A844

Amend 24 to License NPF-63,revising Tech Specs to Delete Surveillance Requirements to Verify Operability of Autoclosure Interlock for RHR Sys Suction/Isolation Valves on High RCS Pressure

ML18009A844
Person / Time
Site:	Harris
Issue date:	03/04/1991
From:	Adensam E, Lo R Office of Nuclear Reactor Regulation
To:
Shared Package
ML18009A845	List: ML18009A844
References
NPF-63-A-024 NUDOCS 9103180475
Download: ML18009A844 (12)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, Dq C. 20555 CAROLINA POWER 5 LIGHT COMPANY et al.

DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

24 License No. NPF-63 1.

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

A.

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

dated November 16,1990, as supplemented December 21, 1990, 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.

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-63 is hereby amended to read as follows:

9>0SS80m5 910S0O PDR ADOCN, 05000400 P

PDR

(2)

Technical S ecifications 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. 24, are hereby incorporated into this license.

Carolina Power 5 Light Company 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 and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical

. Specifications Date of Issuance:

March 4, 1991 Orignal Signed By:

Ronnie Lo 'for:

Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation io C:LA il NAME.:PAn A)JE',:

2 RPR: PN: PD21: DRPR:

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ATTACHMENT TO LICENSE AMENDMENT NO.

24 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 5-3 3/4, 5-4 3/4 5-5 3/4 5-6 Inser t Pa es 3/4 5-3 3/4 5-4 3/4 5-5 3/4 5-6

EMERGENCY CORE COOLING SYSTEMS 3/4.5 '

ECCS SUBSYSTEMS "

T GREATER THAN OR EQUAL TO 350'F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE Charging/safety injection pump, b.

One OPERABLE RHR heat exchanger, c.

One OPERABLE RHR pump, and d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety Injection signal

and, upon being manually aligned, transferring suction to the containment sump during the recirculation phase of. operation.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

With one ECCS 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 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 6

hours'.

In the event the ECCS is actuated and injects water into the Reactor Coolant

System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-

'ing the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

SURVEILLANCE RE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a ~

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by.'

I 1.

Verifying that the following valves are in the indicated positions with the control power disconnect switch in the "OFF" position, and the valve control switch in the "PULL TO LOCK" position:

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

EMERGENCY CORE COOLING SYSTEHS SURVEILLANCE RE UIREHENTS (Continued) d.

At least once per 18 months by:

l.

Verifying automatic interlock action of the RHR system from the Reactor Coolant System by ensuring that with a simulated or actual React, or Coolant System pressure signal greater than or equal to 425 psig the interlocks prevent the valves from being opened.

2.

A visual inspection of each containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks,

screens, etc.)

show no evidence of structural distress or abnormal corrosion.

e.

At least once per 18 months, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on safety injection actuation test signal and on safety injection switchover to containment sump from an RWST Lo-Lo level test signal, and 2.

Verifying that each of the following pumps start automatically upon receipt of a safety injection actuarion test signal:

a)

Charging/safety injection pump, b)

RHR pump.

f.

By verifying that each of the following pumps develops the required differential pressure when tested pursuant to Specification 4.0.5:

l.

Charging/safety injection pump (Refer to Specitication 4. 1.2.4) 2.

RHR pump

> 100 psid at a flow rate of at least 3663 gpm.

g.

By verifying that the locking mechanism is in place and locked for the following High Head ECCS throttle valves:

1.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2.

At least once per 18 months.

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

24

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

EBASCO Valve No.

CP&L Valve No.

2SI-V440SA-1 2SI"V439SB-1 2S I-V438SA-1 2SI-V437SA-1 2S I"V4 36 SB-1 2SI-V435SA-1 2SI-V434SA-1 2SI-V433SB-1 2SI-V432SA-1 2SI-V431SA-1 2SI-V430SB-1 2SI"V429SA-1 1SI-5 1SI"6 1SI-7 1SI-69 1SI-70 1SI-71 1SI-101 1SI"102 1SI-103 1SI-124 1SI-125 1SI"126 h.

By performing a flow balance test, during shutdown, following com-pl.etion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:

1.

For Charging/safety injection pump lines, with a single pump running:

a)

The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 379 gpm, and b)

The total pump flow rate is less than or equal to 685 gpm.

2.

For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to 3663 gpm.

SHEARON HARRIS - UNIT 1

3/4 5-6 Amendment No.

24

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS (Con tinued )

CP&L Valve No.

1SI-107 EBASCO Valve No..

Valve Function 2SI-V500SA-1 High Head Safety Injection to Reactor Coolant System Hot Legs Valve Position Closed 1SI-86 2SI-V501SB-1 High Head Safety Injection to Reactor Coolant System Hot Legs Closed 1SI-52 2SI-V502SA-1 High Head Safety Injection to Reactor Coolant System Cold Legs Closed 1SI-340 2SI-V579SA-1 Low Head Safety'njection to Reactor Coolant System Cold Legs Open 1SI"341 2SI-V578SB-1 Low Head Safety Injection to, Open

'Reactor Coolant System Cold Legs 1S I-359 2SI-V587SA-1 Low Head Safety Injection to Reactor Coolant System Hot Legs Closed b.

At least once per 31 days by:

1.

Verifying that the ECCS piping is full of water by venting accessible discharge piping high points, and 2.

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.

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By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1.

For all accessible areas of the containment prior to establish" ing CONTAINMENT INTEGRITY, and 2.

Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.

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

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