ML17139B046

Amend 1 to License NPF-14,deleting Observation Well 2 from UHS Surveillance,Correcting Values in Tech Spec 4.6.5.1 & Providing Clarification to Vols Associated W/Surveillance Testing

ML17139B046
Person / Time
Site:	Susquehanna
Issue date:	09/03/1982
From:	Youngblood B Office of Nuclear Reactor Regulation
To:
Shared Package
ML17139B047	List: ML17139B046 ML17139B048
References
NUDOCS 8209280107
Download: ML17139B046 (12)

Text

PENNSYLVANIA POWER 8I LIGHT COMPANY A LE.'HE.t R

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Amendment No.

1 License No. HPF-14 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for an amendment filed by the Pennsylvania Power Jj'ight Company, dated August 18, 1982; August 23, 1982; September 1,

1982; and September 2,

1982 complies with the standards and requfrements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;

B.

The facility will operate fn conformity with the application, the provisions of the Act, and the 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 (ff) that such activities will be conducted fn compliance with the Commission's r egulatfons; 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 fn accordance <<fth 10 CFR Part 51'f the Commission' regulations and all applicable requirements have been satisfied.

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2.

Accordingly. the license is amended by changes to the Technical Specific(tines as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facf1fty Operating License No. tJPF-14 is hereby amended to read as follows:

(2) Technical S ecfficatfons and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 1, and the Environmental Protection Plan contained in Appendix 8, are her eby incorporated in the lfcense.

PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8209280107 820908 PDR ADOCK 05000387 PDR OFFICE/

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3.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY CONtlISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

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3 1982

'oriainal sic>>4.~~'

ester I. Kintner.-.

B. J. Youngblood, Chief Licensing Branch No.

1 Division of Licensing OFFICEIII SURNAMEQ OATE Q DL:LBk'2

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'I NRC FORM 318 (10.80) NRCM 0240 OFFIC1AL RECORD COPY USG PO: 1S81~r060

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ATTACHNENT TO LICENSE AMENDMENT NO.

1 RA 4

OOCKt.l 0.

Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE 3/4 6-31 3/4 6-32 3/4 7-3 3/4 7-4 3/4 7-7 3/4 7-8 INSERT 3/4 6-31 3/4 6-32 3/4 7-3 3/4 7-4 3/4 7-7 3/4-7-8 OFFICEI SURNAME/

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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USOFO: 1981~&960

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CONTAINMENT SYSTEMS 3/4.6.5 SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and ".

ACTION:

Without SECONDARY CONTAINMENT INTEGRITY:

a.

In OPERATIONAL CONDITION 1, 2 or 3, restore SECONDARY CONTAINMENT INTEGRITY 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

In Operational Condition

", suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall be demonstrated by:

a.

Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the pressure within the secondary containment is less than or equal to 0.25 inches of vacuum water gauge.

b.

Verifying at least once per 31 days that:

l.

All secondary containment railroad access hatches are closed and sealed or the railroad bay access door is closed.

2.

At least one door in each

'access to the secondary containment ss closed.

3.

All secondary containment penetrations not capable of being closed by OPERABLE secondary containment automatic isolation dampers and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic dampers secured in position.

c.

At least. once per 18 months:

l.

Verifying that one standby gas treatment subsystem will draw down the secondary containment to greater than or equal to 0.25 inches of vacuum water'auge in less than or equal to 60 seconds, and 2.

Operating 'one standby gas treatment subsystem for one hour and maintaining greater than or equal to 0.25 inches of vacuum water gauge in the secondary containment at a flow rate of less than or equal to 2885 cfm from Zone I and Zone III.**

When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

'*2000 cfm while the secondary containment interim barrier is installed in Zone

III, SUSQUEHANNA - UNIT 1 3/4 6-31 Amendment No. I

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOMATIC ISOLATION DAMPERS LIMITING CONDITION FOR OPERATION 3.6.5.2 The secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.2-1 shall be OPERABLE with isolation times less than or equal to the times shown. in Table 3.6.5.2-1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and ".

ACTION:

With one or more of the secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.2-1 inoperable, maintain at least one isolation damper OPERABLE in each affected penetration that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:

a.

Restore the inoperable damper to OPERABLE status, or b.

Isolate each affected penetration by use of at least one deactivated damper secured in the isolation position, or c.

Isolate each affected penetration by use of at least one closed manual valve or blind flange.

Otherwise, in OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within the next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Otherwise, in Operational Condition

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suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.6.5.2 Each secondary containment ventilation system automatic isolation damper shown in Table 3.6.5.,2-1 shall be demonstrated OPERABLE:

a ~

Prior to returning the damper to service after maintenance, repair or replacement work is performed on the damper or its associated

actuator, control or power circuit by cycling the damper through at least one complete cycle of full travel and verifying the specified isolation time.

b.

During COLD SHUTDOWN or REFUELING at least "once per 18 months by verifying that on a containment isolation test signal each isolation damper actuates to its isolation position.

c.

At least once per 92 days by verifying the isolation time to be within its 1 imit.

"For Zone III dampers when irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

'US(UEHANNA

- UNIT 1 3/4 6-32

PLANT SYSTEMS ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.1.3 The spray pond shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and ".

ACTION:

With the groundwater level at any spray pond area observation well greater than or equal to 663'SL, in lieu of any other-report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the high groundwater level and the plans for restoring the level to within the limit.

b.

With the spray pond otherwise inoperable:

1.

In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'.

2.

In OPERATIONAL CONDITION 4 or 5, declare the RHRSW system and the emergency service water system inoperable and take the ACTION required by Specifications 3.7.1. 1 and 3.7. 1.2.

3.

In Operational Condition ", declare the emergency service water system inoperable and take the ACTION required by Specification 3.7.1.2.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.1.3 aO b.

c ~

The spray pond shall be determined OPERABLE by verifying:

The average water temperature, which shall be the arithmetical average of the spray pond water temperature at the surface, m'id and bottom

levels, to be less than or equal to 88'F at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The water level at the.overflow weir. is greater than or equal to 677'ean Sea Level USGS (MSL), 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 water level is < 677'6" MSL, and 2.

14 days when water level is > 677'6" MSL...

The groundwater level at observation'wells I, 3, 4, 5, 6, and 1113 to be less than 663'SL at least once per 31 days.

"When handling irradiated fuel in the secondary containment.

SUSQUEHANNA - UNIT 1 3/4 7-3 Amendment No. I

PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room emergency outside air supply system subsystems shall be OPERABLE with each subsystem consisting of:

a.

One makeup'fan, and b.

One filter train.

APPLICABILITY: All OPERATIONAL CONDITIONS and ".

ACTION:

a.

In OPERATIONAL CONDITION 1, 2 or 3 with one control room emergency outside air supply subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

In OPERATIONAL CONDITION 4, 5 or ":

1.

With one control room emergency outside air supply subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the pressurization mode of operation.

2.

With both control room emergency outside air supply subsystems inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.

, c.

The provisions of Specification 3.0.3 are not applicable in Operational Condition ".

SURVEILLANCE RE UIREMENTS 4.7.2 Each control room emergency outside air supply subsystem shall be demonstrated OPERABLE:

At least onc'e per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least

'10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters OPERABLE.

b.

At least once per 18 months or (1) after any structural thaintenance on the HEPA filter or charcoal adsorber

housings, or (2) following painting, fire or chemical release in any ventilatjon zone communicating with the subsystem by:

l.

Verifying that with the subsystem operating at a flow rate 'of 5810 cfm + lOX and exhausting through the HEPA filters and charcoal adsorbers, the total bypass flow of the system to the facility vent, including leakage through the subsystem diverting valve, is less than or equal to 1X when the subsystem is tested by admitting cold DOP at the system intake.

"When irradiated fuel is being handled in the secondary containment.

SUSQUEHANNA - UNIT 1 3/4 7-4

PLANT SYSTEMS 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 The reactor core isolation cooling (RCIC) system shall be OPERABLE with an OPERABLE flow path capable of taking suction from the suppression pool and transferring the water to the reactor pressure vessel.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome pressure greater than 150 psig.

ACTION:

With the RCIC system inoperable, operation may continue provided the HPCI system is OPERABLE; restore the RCIC system to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to less than or equal to 150 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE UIREMENTS

'.7.3 The RCIC system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

l.

Verifying that the system piping from the pump discharge valve to the system isolation valve is filled with water by:

a.

Venting at the high point vents.

b. 'erformance a CHANNEL FUNCTIONAL TEST of the condensate transfer pump discharge low pressure alarm instrumentation.

2.

Verifying that each valve, manual, power operated or automatic in the flow path that is not locked, sealed or otherwise secured

'n position, is in its correct position.

3.

Verifying that the pump flow controller. is in the correct position.

b.

At least once per 92 days by verifying that the RCIC pump develops a

flow of greater than or equal to 600 gpm in the test flow path w'ith a system head corresponding to reactor vessel operating pressure when steam is being supplied to the turbine at 920 + 140, - 0 psig:"

The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

SUSQUEHANNA - UNIT 1 3/4 7-7

PLANT SYSTEMS SURVEILLANCE RE UIREHENTS Continued) c.

At least once per 18 months by:

1.

Performing a system functional test which includes simulated automatic actuation and restart and verifying that each automatic valve in the flow path actuates to its correct position, but may exclude actual injection of coolant into the reactor vessel.

2.

Verifying that the system will develop a flow of greater than or equal to 600 gpm in the test flow path when steam is supplied to the turbine at a pressure of 150,

+ 15, -0 psig."

3.

Verifying that the suction for the RCIC system is automatically transferred from the condensate storage tank to the suppression pool on a condensate storage tank water level-low signal.

Performing a

CHANNEL CALIBRATION'of the condensate transfer pump discharge low pressure alarm instrumentation and verifying the low pressure alarm setpoint to greater than or equal to 113 psig.

The proves)ons of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the tests.

SUSQUEHANNA --UNIT 1 3/4 7-8, Amendment No. I