ML20092G666

Amend 42 to License NPF-86,revising App a TSs Re Core Reactivity Control Available from Borated Water Sources

ML20092G666
Person / Time
Site:	Seabrook
Issue date:	09/14/1995
From:	Mckee P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20092G668	List: ML20092G666 ML20092G675
References
NUDOCS 9509200024
Download: ML20092G666 (10)

Text

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p y-4 UNITED STATES j

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 206t50001 9 * *.,*,o 1

NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET Al*

+

DPCKET NO. 50-443 SEABROOK STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. NPF-86 i

1.

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

A.

The application for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated June 16, 1995, 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; 4

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 i

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.

9507200024 950914 PDR ADOCK 05000443 P

PDR

i 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the 4ttachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-86 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 42, 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 prior to entering MODE 4 following the fourth refueling outage.

FOR THE NUCLEAR REGULATORY COMISSION Phillip F. McKee, Director Project Directorate I-3 l

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 14, 1995

m_

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ATTACHMENT TO LICENSE AMENDMENT NO. 42 FACILITY OPERATING LICENSE NO. NPF-86 i

DOCKET NO. 50-443 Replace the following pages of Appendix A, Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment number and contain vertic31 lines indicating the areas of change.

Overleaf pages have been provided Remove Insert 3/4 1-11 3/4 1-11 3/4 1-12 3/4 1-12 3/4 5-1 3/4 5-1 3/45-2*

3/4 5-2*

3/4 5-11 3/4 5-11 B 3/4 1-3 B 3/4 1-3 8 3/4 1-4*

B 3/3 1-4*

REACTIVITY CONTROL SYSTEMS BORATION SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION j

3.1.2.5 As a minimum, one of the following borated water sources shall be j

OPERABLE:

l a.

A Boric Acid Storage System with:

1)

A minimum contained borated water volume of 6,500 gallons, l

2)

A minimum boron concentration of 7000 ppe, and 1

3)

A minimum solution temperature of 65'F.

i b.

The refueling water storage tank (RWST) with:

j 1)

A minimum contained borated water volume of 24,500 gallons, 2)

A minimum boron concentration of 2700 ppe, and l

3 3)

A minimum solution temperature of 50*F.

i APPLICABILITY: MODES 5 and 6.

\\

i ACTION:

With no borated water source OPERABLE, suspend all operations involving CORE i

ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS i

4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by-1)

Verifying the baron concentration of the water, 2)

Verifying the contained borated water volume, and 3)

Verifying the boric acid storage tank solution temperature when it is the source of borated 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.

A i

SEABROOK - UNIT 1 3/4 1-11 Amendment No. 42

REACTIVITY CONTROL SYSTEMS BORATION SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 As a minimum, the following borated water sources shall be OPERABLE as required by Specification 3.1.2.,2:

a.

A Boric Acid Storage System with:

1)

A minimum contained borated water volume of 22,000 gallons, 2)

A minimum boron' concentration of 7000 ppe, and 3)

A minimum solution temperature of 65'F.

b.

The reft.eling water storage tank (RWST) with:

1)

A minimum contained borated water volume of 477,000 gallons, 2)

A boron concentration between 2700 and 2900 ppe, l

3)

A minimum solution temperature of 50*F, and 4)

A maximum solution temperature of 98'F.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With the Boric Acid Storage System inoperable and being used as one of the above required borated water sources, restore the system 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 borated to a SHUTDOWN MARGIN equivalent to at least the limit specified in the CORE OPERATING LIMITS REPORT (COLR) for the above MODES at 200*F; restore the Boric Acid Storage System to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the RWST inoperable, restore the tank to OPERABLE status within I hour 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SEABROOK - UNIT 1 3/4 1-12 Amendment g. 42 l

i

)

3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS HOT STANDBY. STARTUP. AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.5.1.1 Each Reactor Coolant System (RCS) accumulator shall be OPERABLE with:

a.

The isolation valve open and power removed, b.

A contained bora.ted water volume of between 6121 and 6596 gallons, c.

A boron concentration of between 2600 and 2900 ppe, and l

d.

A nitrogen cover-pressure of between 585 and 664 psig.

APPLICABILITY: MODES 1, 2, and 3*.

ACTION:

a.

With one accumulator inoperable, except as a result of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 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 reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With one accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve 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 reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

With one pressure or water level channel inoperable per accumulator, return the inoperable channel to OPERABLE status within 30 days or be in at inst 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

d.

With two pressure channels or two water level channels inoperable per accumulator, immediately declare the affected accumulator (s) inoperable.

SURVEILLANCE REOUIREMENTS 4.5.1.1 Each accumulator shall be demonstrated OPERABLE:

a.

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:

1)

Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and

• Pressurizer pressure above 1000 psig.

SEABROOK - UNIT 1 3/4 5-1 Amendment No. 42

EMERGENCY CORE COOLING SYSTEMS ACCUMULATORS HOT STANDBY. STARTUP. ~4D POWER OPERATION 1

SURVEILLANCE REQUIREMENTS 4.5.1.1 (Continued) l 2)

Verifying that each accumulator isolation valve is open.

b.

By verifying the boron concentration of the accumulator solution under the following conditions:

1)

At least once per 31 days, i

2)

Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume. This surveillance is not required when the volume increase makeup source is the RWST and the RWST has not been diluted since verifying that the RWST boron concentration is equal to or greater than the accumulator boron concentration limit.

c.

At least once per 31 days when the RCS pressure is above 1000 psig by verifying that power to the isolation valve operator is disconnected.

d.

At least once per 18 months by verifying that ea:h accumulator isolation valve opens automatically under each r.f the following conditions:

1 1)

When an actual or a simulated RCS pressare signal exceeds the P-11 (Pressurizer Pressure Block of Safety Injection)

Satpoint, and Upon receipt of a Safety Injection test signal.

l 2) i 1

SEABIIOOK - UNIT 1 3/4 5-2 Amendment No. 30

BORON INJECTION SYSTEM 3/4.5.4 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION i

3.5.4 The refueling water storage tank (RWST) shall be OPERABLE with:

a.

A minimum contained borated water volume of 477,000 gallons, b.

A boron concentration between 2700 and 2900 ppm of b'oron, l

c.

A minimum solution temperature of 50*F, and d.

A maximum solution temperature of 98'F.

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

i ACTION:

With the RWST inoperable, restore the tank to OPERABLE status within I hour 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 REOUIREMENTS 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.

I SEABROOK - UNIT 1 3/4 5-11 Amendment No. 42 l

i l

REACTIVITY CONTROL SYSTEMS i

BASES l

l 3/4.1.2 B0 RATION SYSTEMS (Continued) i boron capability requirement occurs at EOL from full power equilibrium xenon l

conditions and requires 22,000 gallons of 7000 ppm borated water from the boric acid storage tanks or a minimum contained volume of 477,000 gallons of

]

2700 - 2900 ppm borated water from the refueling water storage tank (RWST).

l The limitation for a maximus'of one centrifugal charging' pump to be j

OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable in MODES 4, 5, and 6 provides I

assurance that a mass addition pressure transient can be relieved by operation of a single PORV or an RHR suction relief valve.

)

As a result of this, only one boron injection system is available. This 1

is acceptable on the basis of the stable reactivity condition of the reactor, the emergency power supply requirement for the OPERABLE charging pump and the l

additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.

The boron capability required below 200*F is sufficient to provide a j

SHUTDOWN MARGIN as specified in the CORE OPERATING LIMITS REPORT after xenon, decay and cooldown from 200* F to 140* F.

inis condition requires a minimum l

contained volume of 6500 gallons of 7000 ppe borated water from the boric acid storage tanks or a minimum contained volume of 24,500 gallons of 2700 ppm l

borated water from the RWST.

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

i i

The limits on contained water volume and baron 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 l

iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The OPERABILITY of one Boron Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.

l The limitations on OPERABILITY of isolation provisions for the Boron i

Thermal Regeneration System and the Reactor Water Makeup System in Modes 4, 5, i

and 6 ensure that the boron dilution flow rates cannot exceed the value assumed in the transient analysis.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that:

(1) acceptable power 1

distribution limits are maintained, (2).the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of rod misalignment on associated accident analyses are limited. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits. Verification 2

that the Digital Rod Position Indicator agrees with the demanded position l

SEABROOK - UNIT 1 B 3/4 1-3 Amendment No. 42 1

4 i

~

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL ASSEMBLIES (Continued) within i 12 steps at 24, 48, 120, and 228 steps withdrawn for the Control Banks and 18, 210, and 228 steps withdrawn for the Shutdown Banks provides assurances that the Digital Rod Position Indicator is operating correctly over the full range of indication. Since the Digital Rod Position Indication System does not indicate the actual shutdown rod position between 18 steps and 210 steps, only points in the indicated ranges are picked for verification of agreement with demanded position.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires measurement of peaking factors and a restriction in THERMAL POWER. These restrictions provide assurance of fuel rod integrity during continued operation.

In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in' the safety analyses. Measurement with rods at their individual mechanical fully withdrawn position, T greater than or equal to 551*Fandallreactorcoolantpumpsoperatingens,u7esthatthemeasureddrop times will be representative of insertion times experienced during a Reactor trip at operating conditions.

The fully withdrawn position of shutdown and control banks can be varied between 225 and the mechanical fully withdrawn position (up to 232 steps),

inclusive. An engineering evaluation was performed to allow operation to the 232 step maximum. The 225 to 232 step interval allows axial repositioning to minimize RCCA wear.

Control rod positions and OPERABILITY of the rod position indicators a e required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more fr -

quent verifications required if an automatic monitoring channel is inoperabl e.

These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.

For Specification 3.1.3.1 ACTIONS b. and c., it is incumbent upon the plant to verify the trippability of the inoperable control rod (s).

j Trippability is defined in Attachment C to a letter dated December 21, 1984, from E. P. Rahe (Westinghouse) to C. 0. Thomas (NRC). This may be by verification of a control system failure, usually electrical in nature, or that the failure is associated with the control rod stepping mechanism.

In the event the plant is unable to verify the rod (s) trippability, it must be assumed to be untrippable and thus falls under the requirements of ACTION a.

Assuming a controlled shutdown from 100% RATED THERMAL POWER, this allows i

i approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for this verification.

l 1

SEABROOK - UNIT 1 B 3/4 1-4 Amendment No. 8 9