ML20024J203

Amend 32 to License NPF-86,revising App a Re Operability Requirements for Primary Component Cooling Water Sys & Ultimate Heat Sink

ML20024J203
Person / Time
Site:	Seabrook
Issue date:	10/05/1994
From:	Mckee P Office of Nuclear Reactor Regulation
To:
Shared Package
ML20024J204	List: ML20024J203 ML20024J205
References
NUDOCS 9410120144
Download: ML20024J203 (15)

Text

1. "C%g lt UNITED STATES go a

E NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 2055HX)01 l

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NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL" DOCKET NO. 50-443 SfABROOK STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. NPF-86 1.

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

A.

The applications for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated February 26, 1993, and April 7, 1993, as modified by letters dated March 11, 1994, and February 24, 1994, comply with the standards and requirements of the Atomic Energy Act of 1954, as amendad (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.

• North Atlantic Energy Service Company (NAESCO) is authorized to act as agent for the: North Atlantic Energy Corporation, Canal Electric Company, The Connecticut Light and Power Company, Great Bay Power Corporation, Hudson Light and Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, and The United Illuminating Company, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

9410120144 941005 l

PDR ADOCK 05000443 l

P PDR 1

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. 2.

Accordingly, the. license is amenced by changes to the Technical i

Specifications'as indicated in the attachment to this license amendment, i

and paragraph 2.C.(2) of Facility Operating License No. NPF-86 is hereby amended to read as follows:

(2) Technical Soecifications i

The Technical Specifications contained in Appendix A, as revised i

through Amendment No. 32, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No.

NPF-86. NAESCO 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 Phillip F. McKee, Director Project Directorate I-4 i

Division of Reactor Projects - I/II J

Office of Nuclear Reactor Regulation.

Attachment:

Changes to the Technical i

Specifications Date of Issuance: October 5, 1995 l

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ATTACHMENT TO LICENSE AMENDMENT N0. 32 FACILITY OPERATING LICENSE N0. NPF-86 DOCKET NO. 50-443 Replace the following pages of Appendix A, Technical Specifications, with the l

attached pages as indicated. The revised pages are identified by amendment

]

number and contain vertical lines indicating the areas of change. Overleaf pages have been provided.

Remove Insert j

3/4 7-11*

3/4 7-11*

3/4 7-12 3/4 7-12 3/4 7-13 3/4 7-13 3/4 7-13A l

I 3/4 7-138 l

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3/4 7-14 3/4 7-14

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3/4 7-15 3/4 7-15 3/4 7-16*

3/4 7-16*

B 3/4 7-3 8 3/4 7-3 B 3/4 7-3A B 3/4 7-4*

8 3/4 7-4*

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a PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2 The temperatures of both the reactor and secondary coolants in the steam generators shall be greater than 70*F when the pressure of either coolant in the steam generator is greater than 200 psig.

l APPLICABILITY: At all times.

ACTION:

With the requirements of the above specification not satisfied:

1 a.

Reduce the steam generator pressure of the applicable side to less than or equal to 200 psig within 30 minutes, and-b.

Perform an engineering evaluation to determine the effect of the overpressurization on the structural integrity of the steam generator. Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200*F.

SURVEILLANCE REQUIREMENTS 4.7.2 The pressure in each side of the steam generator shall be determined to l

be less than 200 psig at least once per hour when the temperature of either the reactor or secondary coolant is less than 70*F.

t SEABROOK - UNIT 1 3/4 7-11

PLANT SYSTEMS 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM LlMITING CONDITION FOR OPERATION 3.7.3 At least two independent primary component cooling water loops shall be OPERABLE, including one OPERABLE pump in each loop.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one primary component cooling water (PCCW) loop inoperable, restore the required primary component cooling water loop 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 COLD 1

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

I SURVEILLANCE REOd!REMENTS 4.7.3 At least two primary component cooling water loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and j

b.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to its correct position on its associated Engineered Safety Feature actuation signal.

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f SEABROOK - UNIT 1 3/4 7-12 Amendment No. 32

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM / ULTIMATE HEAT SINK l

LIMITING CONDITION FOR OPERATION 3.7.4 The Service Water System shall be OPERABLE with:

An OPERABLE service water pumphouse and two service water loops with a.

one OPERABLE service water pump in each loop, b.

An OPERABLE mechanical draft cooling tower and two cooling tower service water loops with one OPERABLE cooling tower service water pump in each loop, and A portable cooling tower makeup system stored in its design c.

operational readiness state.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one service water loop inoperable, return the loop to OPERABLE a.

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 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 />.

b.

With one cooling tower service water loop or one cooling tower cell inoperable, return the affected loop or cell to OPERABLE status within 7 days, 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 />, With two cooling tower service water loops or the mechanical draft c.

cooling tower inoperable, return at least one loop and the mechanical draft cooling tower 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 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 />.

d.

With two loops (except as described in c) or the service water pumphouse inoperable, return at least one of the affected loops and the service water pumphouse to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 />.

With the portable tower makeup pump system not stored in its design e.

operational readiness state, restore the portable tower makeup pump system to its required condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or continue operation and notify the NRC within the following I hour in accordance with the requirements of 10 CFR 50.72 of actions to ensure an adequate supply of makeup water for the service water cooling tower for a minimum of 30 days.

SEABROOK - UNIT I 3/4 7-13 Amendment No. 32 l

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PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM / ULTIMATE HFAT SINK l

SURVEILLANCE RE0VIREMENTS 4.7.4.1 Each service water loop shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, a.

power-operated, or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and b.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to its correct position on its associated Engineered Safety Feature actuation test signal.

4.7.4.2 Each service water cooling tower loop shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, a.

power-operated, or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and b.

At least once per 10 months during shutdown, by verifying that:

1)

Each automatic valve servicing safety-related equipment actuates to its correct position on its associated Engineered Safety Feature actuation test signal, 2)

Each automatic valve in the flowpath actuates to its correct position on a Tower Actuation (TA) test signal and 3)

Each service water cooling tower pump starts automatically on a TA signal.

4.7.4.3 The service water pumphouse shall be demonstrated OPERABLE 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 water level to be at or above 5'-0" (-36'-0" Mean Sea Level).

4.7.4.4 The mechanical draft cooling tower shall be demonstrated OPEPABLE:

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 water in the mechanical a.

draft cooling tower basin to be at a level of greater than or equal to 42.15* feet.

b.

At least once per week by verifying that the water in the cooling tower basin to be at a bulk average temperature of less than or equal to 70*F.

• With the cooling tower in operation with valves aligned for tunnel heat treatment, the tower basin level shall be maintained at greater than or equal to 40.55 feet.

SEABROOK - UNIT 1 3/4 7-13A Amendment No. 32

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM /UTIMATE HEAT SINK l

SURVEILLANCE RE0VIREMENTS c.

At least once per 31 days by:

1)

Starting from the control room each cooling tower fan that is required to be OPERABLE and operating each of these fans for at least 15 minutes, and 2)

Verifying that the portable tower makeup pump system is stored in its design operational readiness state.

d.

At least once per 18 months by verifying that the portable tower makeup pump develops a flow greater than or equal to 200 gpm.

SEABROOK - UNIT 1 3/4 7-13B Amendment No. 32

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PLANT SYSTEMS

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I 3/4.7.5 (THIS SPECIFICATION NUMBER IS NOT USED)

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I PAGE INTENTIONALLY BLANK SEABROOK - UNIT I 3/4 7-15 Amendment No. 32

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PtANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY MAKEUP AIR AND FILTRATION SUBSYSTEM f

LIMITING CONDITION FOR OPERATION i

3.7.6 Two independent Control Room Emergency Makeup Air and Filtration Subsystems shall be OPERABLE.

{

i APPLICABILITY: All MODES l

ACTION:

l MODES 1, 2, 3 and 4:

4 With one Control Room Emergency Makeup Air and Filtration Subsystem inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at i

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

i MODES 5 and 6:

a.

With one Control Room Emergency Makeup Air and Filtration Subsystem i

inoperable, restore the inoperable system to OPERABLE status within 7 i

days or initiate and maintain operation of the remaining OPERABLE i

Control Room Emergency Makeup Air and Filtration Subsystem in the filtration / recirculation mode.

l b.

With both Control Room Emergency Makeup Air and Filtration Subsystems

(

inoperable, or with the OPERABLE Control Room Emergency Makeup Air and Filtration Subsystem, required to be in the filtration / recirculation mode by ACTION a., not capable of being powered by an OPERABLE emergency power source, suspend all operations solving CORE ALTERATIONS or positive reactivity changes.

i SURVEILLANCE RE0VIREMENTS 4.7.6 Each Control Room Emergency Makeup Air and Filtration 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 verifying that the control room is l

maintained below the limiting equipment qualification temperature in i

the control room area.

i b.

At least once 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 system operates for at least 10 continuous hours with the heaters operating; l

SEABROOK - UNIT 1 3/4 7-16

PLANT SYSTEMS EASES

}/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70*F and 200 psig are based on a steam generator RT, of 60*F and are sufficient to prevent brittle fracture 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Primary Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

3/4.7.4 SERVICE WATER SYSTEM / ULTIMATE HEAT SINK l

The Service Water System consists of two independent loops, each of which can operate with either a service water pump train or a cooling tower pump train.

Each service water loop consists of a service water pump and the piping, valves, and other components necessary to provide the flowpath required for heat removal.

Each service water cooling tower loop consists of a service water cooling tower pump and the necessary piping, valves and other components required to provide its flowpath. The OPERABILITY of the Service Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses, which also assumes loss of either the cooling tower or ocean cooling.

Cooling is normally provided by the Atlantic Ocean via the service water pumphouse. A seismically qualified mer.hanical draft cooling tower is provided as a backup to the ocean cooling water source because the supply from the circulating water tunnels is not seismically qualified. The mechanical draft cooling tower was designed to use three cells to support two units. Unit I utilizes two train-related cells; cell 1 serves Train A and has a single fan, the common cell serves Train B and has two fans. The cooling tower design basis is to provide the necessary ultimate heat sink in the event of a loss of ocean tunnel water flow; however, this source may be used during normal operations subject to the level and temperature limitations of this specification.

Switchover from the service water pumphouse to the mechanical draft cooling tower is accomplished either automatically (Tower Actuation (TA) signal) or manually. Manual action is required to realign the system from the cooling tower to the service water pumphouse. While a cooling tower pump is operating, interlocks prevent the train associated service water pumps from starting.

To provide additional protection, during operation while aligned to the cooling tower, the service water pump control switches may be maintained in the pull-to-lock position to prevent inadvertent pump operation. As previously SEABROOK - UNIT 1 B 3/4 7-3 Amendment No. 32

' PLANT SYSTEMS BASES 3/4.7.4 SERVICE WATER SYSTEM / ULTIMATE HEAT SINK (Continued) discussed, realignment to the service water pumphouse requires manual action; maintaining the control switches in the pull-to-lock position does not change this required action sequence.

Pump operation is not affected by maintaining the control switches in the pull-to-lock position during this period; therefore, OPERABILITY of the service water pumps is not compromised.

The limitations on service water pumphouse minimum water level and the requirements for cooling tower OPERABILITY are based on providing a 30-day cooling water supply to safety-related equipment without exceeding the safety related equipment design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants," Harch 1974.

The Cooling Tower is normally aligned to allow return flow to bypass the tower sprays and return to the basin.

In addition, the control switches for the cooling tower fans are normally maintained in the " pull-to-lock" position.

Upon receipt of a Tower Actuation Signal, the fans and sprays are manually operated as required.

This manual operation, which is governed by procedures, ensures that ice does not buildup on the cooling tower tile fill and fans. The cooling tower basin temperature limit of 70*F provides sufficient time for manual initiation of the cooling tower sprays and fans following the design basis seismic event with a concurrent LOCA, during the design extreme ambient temperature conditions. Under this scenario, manual action is sufficient to maintain the cooling tower basin at a temperature which precludes equipment damage during the postulated design basis event.

3/4.7.5 (THIS SPECIFICATION NUMBER IS NOT USED) i 1

l SEABROOK - UNIT 1 B 3/4 7-3A Amendment No. 32

PLANT SYSTEMS BASES 3/4.7.6 CONTROL ROOM EMERGENCY MAKEUP AIR AND FILTRATION SUBSYSTEM The OPERABILITY of the Control Room Emergency Makeup Air and Filtration Subsystem ensures that:

(1) the allowable temperature for continuous-duty rating for the equipment and instrumentation cooled by this system is not exceeded; and (2) the control room will remain habitable for operations personnel during and following credible accident conditions. Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. Heaters run continuously to maintain the relative humidity below 70%.

The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rems or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50. ANSI N510-1980 will be used as a procedural guide for surveillance testing.

3/4.7.7 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.

Snubbers are classified and grouped by design and manufacturer but not by size.

For example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip and 100-kip capacity manufactured by Company "A" are of the same type.

The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.

A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Station Operation Review Committee (50RC).

The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.

The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

Surveillance to demonstrate OPERABILITY is by performance of the require-ments of an approved inservice inspection program.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.

Snubbers so exempted SEABROOK - UNIT 1 B 3/4 7-4

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