Text

Amend 8 to License NPF-86,changing Tech Spec for Facility to Redefine Fully Withdrawn Position of All Rcca Banks to Minimize Localized Rcca Wear
	ML20086D679
Person / Time
Site:	Seabrook
Issue date:	11/18/1991
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20086D682	List: ML20086D679; ML20086D687;
References
	NUDOCS 9111260220
	Download: ML20086D679 (7)
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UNITED STATES 8%

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NUCLEAR REGULATORY COMMISSION

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PUBLIC_ SERVICE COPPANY OF NEW HAMPSHIRE, ET AL.*

DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No. NPF-16 1.

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

A.

The application for amend:nent filed oy the Public Service Company of New Hampshire (the licensee), acting for itself and as agent and representative of the 11 other utilities listed below and hereafter referred to as licensees, dated April 12, 1991, and supplemented July 12, 1991 comply with the standards and requirements oftheAtomicEnergyActof1954,asamended(theAct),andthe Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the orovisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance: (1) 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 set forth in 10 CFR Chapter I; 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 regt.lations and all applicable requirements have been satisfied.

Putlic 5ervice Company of New Hampshire is authorized to act as agent for the:

I Canal Electric Cor-pany, The Connecticut Light and Power Company, EUA Power Corporation, Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, The United illuminating Cxpany, and Vermont Electric Generation and Transr srion d

Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operatien and maintenance of the f acility.

9111260DDc 91jj19 DR ADOCK 00,0004g UDH

. 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-86 is hereby amended to read as follows:

(2) Technic g Specifications, The Technical Specifications contained in Appendix A, as revised through Amendment No. B, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No.

NPF-86. PSNH shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendn.ent is effective as of its date of issuance and shall be implemented within 60 days of receipt of this letter.

FOR THE NUCLEAR REGULATORY COMMISSION 1

Walter R. Butler, Director Project Directorate 1-3 Division nf Reactor Projects - 1/11 Office of f:ui. lear Reactor Regulation

Attachment:

Changes to the Technical Specifications 4

Date of issuence: November 18, 1991

AVTACHMENT TO LICEN50 AMENDMENT NO 8 l

FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO 50 443 Replace the following pages of the Appendix A Technical Specifications with the attached pages.

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

Remove

.Lnsd 3/4 1-20 3/4 1 20 3/4 1-21 3/4 1-21 3/4 1-23 3/4 1-23 8 3/4 1-4 8 3/4 1-4 l

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REACTIVITY CONTROL SYSTEMS j

MOVABLE CONTROL ASSEMBLIES POSITION INDICATION SYSTEM - SHUTDOWN LIMITING CON 0! TION FOR OPERATION

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3.1.3.3 One digital rod position indicator (exc1 ding demand position e

indication) shall be OPERA 8LE and capable of detereining the control rod i

position within i 12 steps for each shutdown or control rod not fully 4

inserted.

APPLICABILITY:

MODE $ 3* **, 4* **, and $* **.

ACTION:

With less than the above required position indicator (s) OPERA 8LE. immediately i

open the Reactor Trip System breakers.

i SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required digital rod position indicator (s) shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 steps when exercised over the full range of rod travel at least once per 18 months.

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With the Reacto Trip System breakers in the closed position.

- See Special Test Exceptions Specification 3.10.5.

SEABROOK - UNIT 1 3/4 1-19

b REACTIVITY CONTROL SYSTEMS MOVABLE CONTROL ASSEMBLIES ROD DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length (shutdown and control) rod drop time from the mechanical fully withdrawn position shall be less than or equal to 2.2 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

T,yg for each loop greater than or equal to SS1'F, and a.

b.

All reactor coolant pumps operating.

APPLICABILITY:

MODES 1 and 2.

MTION:

With the drop time of any full-length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

SURVEILLANCE REQUIREMEN15 4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:

s.

For all rods following each removal of the reactor vessel Iaad, b.

For specifically affected individual rods following any maintanence on or modification to the Control Rod Drive System that could affect the drop time of those specific rods, and c.

At least once per 18 months.

SEABROOK - UNIT 1 3/4 1-20 Amendment No. 8

REACTIVITY CONTROL SYSTEMS HOVABLE CONTROL ASSEMBLIES SHUT 00WN ROD INSERTION LIMIT LIMITING CONDITION FOR OPERATION

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3.1.3.5 All shutdown rods shall be fully withdrawn #.

APPLICABILITY:

MODES 1* and 2* **.

ACTION:

With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either:

Fully withdraw # the rod, or l

a.

b.

Declare the rod to be inoperable and apply Specification 3.1. 3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn #:

l a.

Within 15 minutes prior to withdrawal of any rods in Control Bank A, B, C, or 0 during an approach to reactor criticality, and b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

Sse Special Test Exceptions Specifications 3,10.2 and 3.10.3.

- With kgff greater than or equal to 1.

The fully withdrawn position is defined as the iiterval within 225 to the

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mechanical fully withdrawn position, inclusive.

SEABROOK - UNIT 1 3/4 1-21

/pendment No. 8

REACTIVITY CONTROL SYSTEMS MOVABLE CONTROL ASSEMBLIES CONTROL ROD INSERTION LIMITS i

LIMITING CONDITION FOR OPERATION i

3.1.3.6 The control banks shall be limited in physical insertion as shown in Figure 3.1-1.

APPLICABILITY:

MODES la and 2a **.

ACTION:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2:

a.

Restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank posi-tion using the above flgure, or c.

Be in at least' HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , except during time intervals when the rod insertion limit monitor is inoperable; then verify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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See 5?cchs Test Exceptions Specifications 3.10.2 and 3.10.3,

- With k,7f greater than or equal to 1.

SEABROOK -

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3/4 1-22 L.--

BANK A MUST BE FULLY WITHDkAWN* PRIOR TO POWER OPERATION (0.286,225)

(9.830,225) 225*

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I e.0 e.2 0.4 0.6 N8 1.0 FRACTION OF RATED THERMAL POWER FICURE 3.1-1 ROD BANK INSERTION LIMITS VERSUS THERMAL P0%TR FOUR-LOOP OPERATION

Fully Withdrawn = 225 to the machanical fully withdrawn position, inclusive SEABROOK - UNIT 1 3/4 1-23 Amendment No. 8

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 BORATION SYSTEMS (Continued) w The boron capability required below 200*F is sufficient NPjTrsvide a SHVTLOWN MARGIN of 1.2% ak/k af ter xenon decay and cocidwn free 200'F to 140'F.

This condition requires a minimum contained volume of 6500 gallons of 7000 ppm borated water from the boric acid storage tanks or a minimum contained volume of 24,500 gallons of 2000 ppm borated water from the RWST.

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

The limits on contained water volume and boron concentration of the RWST alsu ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band N nimizes the evolution of iodine and minimizes the tffect 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.

The limitations on OPERABILITY of isalation provisions for the Boron Thermal Regeneration System and the Reactor Water Hakeup System in Hofes 3, 4, 5, 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 distri-bution limits are maintained, (2) the minimum SHUTDOVM 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 that the Digital Rod Position Indicator agren with the demanded position within i 12 steps at 24, 48, 120, e

and 228 steps withdrawn for the Control Banks and 18, 210, and 228 steps with-drawn for the Shutcown Banks provides assurances that the Digital Rod Position a

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 indiccted 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 f actors and a restriction in THERMAL POWER.

These restrictions pro-vide 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.

SEABROOK - UNIT 1 B 3/4 1-3 J

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL A SEMBLIES (Continued)

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with rods at their indivi-dual mechanical fully withdrawn position, T,yg greater than or equal to 551'T and all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experiericed 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 maximu.a.

The 225 to 232 step interval allows axial repositioning to minimize RCCA wear.

Control rod positions and OPERABIL1TY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with more fre-quent verifications required if an automatic monitoring channel is inoperable.

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).

Trippability is defined in Attachment C to a letter dated December 21, 1984, from E. P. Rahe (Westinghouse) to C. O. 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.

Assuuiing a controlled shutdown from 100% RATED THERMAL. POWER, this allows approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for this verification.

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

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ML20086D679

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