Text

Amend 27 to License NPF-86 Revises App a TS Re Requirement to Use Movable Incore Detectors to Perform Certain Measurements
	ML20059B029
Person / Time
Site:	Seabrook
Issue date:	12/22/1993
From:	De Agazio A; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20059B031	List: ML20059B029; ML20059B041;
References
	NUDOCS 9401030259
	Download: ML20059B029 (21)
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E UNITED STATES i

NUCLEAR REGULATORY COMMISSION i

Q WASHINGTON, D.C. 20555-0001

....+

NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL*

i DOCKET NO. 50-443 SEABROOK STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE L

Amendment No. 27 License No. NPF-86 1.

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

A.

The application for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated November 25, 1992, as supplemented by letters dated July 2,1993, and November 24, 1993, 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 requiremerus have been satisfied.

' North Atlantic Energy Service Company (NAESCO) is authorized to act as agent l'

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, 1

Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, The United Illuminating Company, and Vermont Electric Generation and Transmission Cooperative, Inc.,

and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

9401030259 931222 i

PDR ADOCK 05000443 P

PDR t

. 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 j

amended to read as follows-

)

(2) Technical Soecifications i

1 The Technical Specifications contained in Appendix A, as revised l

through Amendment No.27, 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 REGULAT0RY COMMISSION j

$ f/

/}kh l

John F. S olz, Directo

/

1 Project Directorate I-4 Division of Reactor Projects - I/II i

Office of Nuclear Reactor Regulation

Attachment:

Changes to the. Technical l

Specifications Date of Issuance:

December 22, 1993 l

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ATTACHMENT TO LICENSE AMENDMENT N0.27 FACILITY OPERATING LICENSE N0. NPF-86 DOCKET NO. 50-443 3

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

Remove Insert iii*

iii*

iv iv 3/4 1-15*

3/4 1-15*

3/4 1-16 3/4 1-16 3/4 1-17*

3/4 1-17*

3/4 1-18 3/4 1-18 3/4 2-5*

3/4 2-5*

l I

3/4 2-6 3/4 2-6 3/4 2-7 3/4 2-7 l

3/4 2-8 3/4 2-8 l

3/4 2-9 3/4 2-9 3/4 2-10*

3/4 2-10*

3/4 3-39*

3/4 3-40 3/4 3-40 B 3/4 2-3 8 3/4 2-3 B 3/4 2-4*

B 3/4 2-4*

B 3/4 3-3*

B 3/4 3-4 B 3/4 3-4 i

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION Pf_GE 3/4.1.2 B0 RATION SYSTEMS Flow Paths - Shutdown 3/4 1-7 Flow Paths - Operating.................

3/4 1-8 i

Charging Pump - Shutdown................

3/4 1-9 Charging Pumps - Operating...............

3/4 1-10 Borated Water Sources - Shutdown............

3/4 1-11 Borated Water Sources - Operating 3/4 1-12 Isolation of Unborated Water Sources - Shutdown 3/4 1-14 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height......................

3/4 1-15 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN IN0PERABLE FULL-LENGTH R00.........

3/4 1-17 Position Indication Systems - Operating 3/4 1-18 i

Position Indication System - Shutdown 3/4 1-19 Rod Drop Time 3/4 1-20 Shutdown Rod Insertion Limit..............

3/4 1-21 Control Rod Insertion Limits..............

3/4 1-22 l

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 3/4 2-1 3/4 2-4 3/4.2.2 HEAT FLUX 40T CHANNEL FACTOR - F[(Z) 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNE FACTOR........

3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-9 3/4.2.5 DNB PARAMETERS.....................

3/4 2-10 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-2 i

t SEABROOK - UNIT 1 iii Amendment No. 9

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t INDEX LIMITING CONDITIONS FOR OPERATION AND SURVElllANCE REQUIREMENTS I

i SECTION PA_G1 TABLE 3.3-2 (This table number is not used)

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................

3/4 3-9

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3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM i

3/4 3-14 INSTRUMENTATION TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM i

3/4 3-16 i

INSTRUMENTATION TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM a

INSTRUMENTATION TRIP SETPOINTS.............

3/4 3-24 TABLE 3.3-5 (This table number is not used) 4

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TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-31 l

3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations 3/4 3-36 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS 3/4 3-37 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS..........

3/4 3-39 Incore Detector System.................

3/4 3-40 l

3/4 3-41 Seismic Instrumentation TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION.........

3/4 3-42 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................

3/4 3-43 Meteorological Instrumentation.............

3/4 3-44 TABLE 3.3-8 ' METEOROLOGICAL MONITORING INSTRUMENTATION 3/4 3-45 i

Remote Shutdown System.................

3/4 3-46 TABLE 3.3-9 REMOTE SMUTDOWN SYSTEM...............

3/4 3-47 Accident Monitoring Instrumentation 3/4 3-49 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION........

3/4 3-50 TABLE 3.3-11 (This table number is not used)..........

3/4 3-53 Radioactive Liquid Effluent Monitoring Instrumentation.

3/4 3-55 TABLE 3.3-12 RAD',DACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-56 i

SEABROOK - UNIT 1 iv Amendment No. 27

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full-length shutdown and control rods shall be OPERABLE and positioned within 12 steps (indicated position) of their group step counter demand position.

APPLICABILITY: MODES 1* and 2*.

ACTION:

I a.

With one or more full-length rods inoperable because of being immovable as a result of excessive friction or mechanical interference or known to be untrippable determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within I hour and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one full-length rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligned from its group step counter demand height by more than i 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within 12 steps of the inoperable rod while maiataining the rod sequence and insertion limits of Specification 3.1.3.6.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or 3.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

a)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation

)

under these conditions-b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

SEABROOK - UNIT 1 3/4 1-15 Amendment No. 9

REACTIVITV CONTROL SYSTEMS MOVABLE CONTROL ASSEMBLIES 1

GROUP HEIGHT l

LIMITING CONDITION FOR OPERATION 3.1.3.1 ACTION b.3 (Continued) c)

A power distribution map is obtained from the Incore Detector System and F (Z) and F"a are verified to be l

q within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and d)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the High Neutron Flux Trip Setpoint is reduced to.less than or equal to 85% of RATED THERMAL POWER.

l c.

With more than one rod trippable but inoperable due to causes i

other than addressed by ACTION a. above, POWER OPERATION may continue provided that-i 1.

Within I hour, the remainder of the rods in the bank (s) with the inoperable rods are aligned to within i 12 l

steps of the inoperable rods while maintaining the rod sequence and insertion limits of Specification 3.1.3.6.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and 2.

The inoperable rods are restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d.

With more than one rod misaligned from its group step counter demand height by more than i 12 steps (indicated position),

be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS l

1 i

4.1.3.1.1 The position of each full-length rod shall be determined to be within the group demand limit by verifying the individual rod positions 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 position deviation monitor is inoperable; then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i 4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

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SEABROOK - UNIT 1 3/4 1-16 Amendment No. 27 1

TABLE 2.1-1 ACCIDENT ANALYSES RE0VIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH ROD Rod Cluster Control Assembly Insertion Characteristics i

Rod Cluster Control Assembly Misalignment.

Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in large Pipes Which Actuates the Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal at Full Power Major Reactor Coolant System Pipe Ruptures (Loss-of-Coolant Accident)

Major Secondary Coolant System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) i 9

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B SEABROOK - UNIT 1 3/4 1-17

i REACTIVITY CONTROL SYSTEMS MOVABLE CONTROL ASSEMBLIES POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 1

l 3.1.3.2 The Digital Rod Position Indication System and the Demand Position Indication System shall be OPERABLE and capable of determining the control rod positions within i 12 steps.

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APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With a maximum of one digital rod position indicator per bank j

inoperable, either:

1.

Determine the position of the nonindicating rod (s) indirectly by the Incore Detector System at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and l

immediately after any motion of the nonindicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

With a maximum of one demand position indicator per bank i

inoperable, either:

i 1.

Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE RE0VIREMENTS 4.1.3.2 Each digital rod position indicator shall be determined to be OPERABLE by verifying that the Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps 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 position deviation monitor is inoperable; then compare the Demand Position Indication System and the Digital Rod Position Indication System at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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SEABROOK - UNIT 1 3/4 1-18 Amendment No. 27 t

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SEABROOK - UNIT 1 3/4 2-5 Amendment No. 9 1

POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR - F,(Z)

LIMITING CONDITION FOR OPERATION 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 F,y shall be evaluated to determine if F (Z) is within its limit by:

a Using the Incore Detector System to obtain a power distribution map l

a.

at any THERMAL POWER greater than 5% of RATED THERMAL POWER, b.

Increasing the measured F component of the power distribution map by3%toaccountformanu7acturingtolerancesandfurther i

increasing the value by 5% when using the movable incore detectors or 5.21% when using the fixed incore detectors, to account for measurement uncertainties.

Comparing the F,y computed (Fly) obtained in Specification c.

4.2.2.2b., above, to:

1)

The F,y limits for RATED THERMAL POWER (F" ") fu ne appropriate measured core planes given inl* Specification i

4.2.2.2e. and f., below, and 1

2)

The relationship:

Fly F"ll [l+PF,y(1-P)],

Where F ' is the limit for fractional THERMAL POWER operation express 5dasafunctionofF"ll,PF is the Power Factor Multiplier for F specified in thdyCOLR and P is the

'i fractionofRATEYTHERMALPOWERatwhichF,y was measured.

d.

Remeasuring F,y according to the following schedule:

measured core plane but less t8lan the F 'yWhen Fl limit for the appropriate 1) relationship, additional power distribution maps shalf be ta' in and F*C compared to F"ll and FI, either:

a)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATED THERMAL POWERorgreater,theTHERMALPOWERatwhichFly was last determined, or b)

At least once per 31 Effective Full-Power Days (EFPD),

whichever occurs first.

9 SEABROOK - UNIT 1 3/4 2-6 Amendment No. 27 i

e POSER DISTRIBUTION LIMITS e

HEAT FLUX HOT CHANNEL FACTOR - F (Z)

SURVEILLANCE RE0VIREMENTS i

4.2.2.2d. (Continued)

WhentheFfy appropriate measured core plane, additional lpoweris less than 2) distribution maps shall be taken and Fly comparedtoF7land r

Fly at least once per 31 EFPD.

all core planes containing Bank "D" controll rods and all unroddedlimits for RATED THERMAL POWER The F,y e.

core planes in the CORE OPERATING LIMITS REPORT per Specification 6.8.1.6; f.

The F limits of Specification 4.2.2.2e., above, are not applic#able in the following core planes regions as measured in percent of core height from the bottom of the fuel:

1)

Lower core region from 0 to 15%, inclusive, 2)

Upper core region from 85 to 100%, inclusive, 3)

Grid plane regions at 17.8 1 2%, 32.1 1 2%, 46.4 i 2%, 60.6 2%, and 74.9 1 2%, inclusive, and i

4)

Core plane regions within i 2% of core height ( 2.88 inches) about the bank demand position of the Bank "D" control rods.

With F l exceeding F ly, if F,(Z) is withi*n" its fimits.

the effects of F on F (Z) shall be g.

evaluated to determine 4.2.2.3 When F,(Z) is measured for other than F determinations, an overall y

measured F,(Z) shall be obtained from a power di,stribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% when using the movable incore detectors or 5.21% when using the fixed incore detectors, to account for measurement uncertainty.

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i SEABROOK - UNIT 1 3/4 2-7 Amendment No. 27

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8 POWER DISTRIBUTION LIMITS 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3. 2. 3 Fl, s h al l be l e s s t h a n F"'l, [ 1. 0 + N,, 0 - N ].

Where:

P=

THERMAL POWER

, and RATED THERMAL POWER F"'[,ified in the l CORE OPERATI.the F, limit at F; 1 THERMAL POWER (RTP),

=

spec IMITS REPORT (COLR),

and thePowerFactorMultiplierforFl, PF g

specified in the COLR.

APPLICABILITY: MODE 1.

ACTION:

With Fl, exceeding its limit:

a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months reduce the THERMAL POWER to the level where the LIMITING CONDITION FOR OPERATION is satisfied.

b.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the limit required b ACTION a.,

above; THERMAL POWER may then be increased, provided F is demonstrated through incore mapping to be within its 1 it.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 Fl, shall be demonstrated to be within its limit prior to operation above 75% RATED THERMAL POWER after each fuel loading and at least once per 31 EFPD thereafter by:

a.

Using the Incore Detector System to obtain a power distribution map l

at any THERMAL POWER greater than 5% RATED THERMAL POWER.

b.

Using the measured value of Fl, which does not include an allowance for measurement uncertainty.

SEABROOK - UNIT 1 3/4 2-8 Amendment No. 27

=

l POBER DISTRIBUTION LIMITS 3/4.2.4 OVADRANT POWER TILT RATIO l

LIMITING CONDITION FOR OPERATION r

~

3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02.

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-APPLICABILITY:

MODE 1, above 50% of RATED THERMAL POWER *.

ACTION:

l With the QUADRANT POWER TILT RATIO determined to exceed 1.02:

a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months reduce THERMAL POWER at least 3% from RATED THERMAL l

POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess l

of 1 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and every 7 days thereafter, verify that F,(Z) (by F

evaluation) and FL are within their limits by performing y

Surveillance Requirements 4.2.2.2 and 4.2.3.2.

THERMAL POWER and setpoint reductions shall then be in accordance with the ACTION statements of Specifications 3.2.2 and 3.2.3.

t SURVEILLANCE RE0VIREMENTS i

4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a.

Calculating the ratio at least once per 7 days when the alarm is OPERABLE, and b.

Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady-state operation when the alarm is inoperable.

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the Incore Detector System to confirm indicated QUADRANT l

POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by either:

i a.

Using the four pairs of symmetric detector locations or l

b.

Using the Incore Detector System to monitor the QUADRANT POWER TILT l

RATIO subject to the requirements of Specification 3.3.3.2.

See Special Test Exceptions Specification 3.10.2 SEABROOK - UNIT 1 3/4 2-9 Amendment No. 27 l

4 POWER DISTRIBUTION LIMITS 3/4,2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the following limits:

Reactor Coolant System T,,, s 594.3*F a.

b.

Pressurizer Pressure, 2 2205 psig*

c.

Reactor Coolant System Flow, 2 392,000 gpm" APPLICABILITY: MODE 1.

i ACTION:

With any of the above parameters exceeding its limit, restore the parameter to i

within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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SURVEILLANCE RE0VIREMENTS 4.2.5.1 Each of the parameters shown above shall be verified to be within its limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1 4.2.5.2 The RCS flow rate indicators shall be subjected to CHANNEL CALIBRATION at least once per 18 months.

4.2.5.3 The RCS total flow rate shall be determined by a precision heat balance measurement to be within its limit prior to operation above 95% of RATED THERMAL POWER after each fuel loading. The provisions of Specification

.i 4.0.4 are not applicable for entry into MODE 1.

4

Litrit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10%

of RATED THERMAL POWER.

- Includes a 2.4% flow measurement uncertainty.

SEABROOK - UNIT 1 3/4 2-10 Amendment No. 12

TABLE 4.3-3 v,

m

$5 RADIATION MONITORING INSTRUMENTATION FOR PLANT E3 OPERATIONS SURVEILLANCE RE0VIREMENTS O*

DIGITAL CHANNEL MODES FOR WHICH EE CHANNEL CHANNEL OPERATIONAL SURVEILLANCE

$1 FUNCTIONAL UNIT CHECK CALIBRATION IEST IS REQUIRED

1. Containment

a. Containment - Post LOCA -

Area Monitor S

R H

All

b. RCS Leakage Detection

1) Particulate Radio-S R

H 1, 2, 3, 4 activity

2) Gaseous Radioactivity S

R H

1, 2, 3, 4

2. Containment Ventilation Isolation

a. On Line Purge Monitor S

R M

1, 2, 3, 4 u,

1s

b. Manipulator Crane Area S

R H

6#

Monitor u,

b$ 3. Main Steam Line S

R H

1, 2, 3, 4

4. Fuel Storage Pool Areas

a. Radioactivity-High-Gaseous Radioactivity S

R H

5. Control Room Isolation

a. Air Intake Radiation Level 1 East Air Intake S

R M

All 2 West Air Intake S

R H

All

6. Primary Component Cooling Water

a. Loop A-S R

H All

b. Loop B S

R M

All TABLE NOTATIONS

With irradiated fuel in the fuel storage pool areas.

During CORE ALTERNATIONS or movement of irradiated fuel within the containment.

l E.

INSTRUMENTATION MONITORING INSTRUMENTATION l

INCORE DETECTOR SYSTEM i

LIMITING CONDITION FOR OPERATION l

?

3.3.3.2 The Incore Detector System shall be OPERABLE with:

)

a.

At least 75% of the detector locations and, b.

A minimum of two detector locations per core quadrant.

j An OPERABLE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of three OPERABLE detectors or an OPERABLE movable incore detector capable of mapping the location.

APPLICABILITY: When the Incore Detector System is used for:

a.

Recalibration of the Excore Neutron Flux Detection System, or b.

Monitoring the QUADRANT POWER TILT RATIO, or Measurement of FL,F,(Z) and F,y c.

ACTION:

With the Incore Detector System inoperable, do not use the system for the above l

applicable monitoring or calibration functions.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS (Plant procedures are used to determine that the Incore Detector System is l

OPERABLE.)

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SEABROOK - UNIT 1 3/4 3-40 Amendment No. 27

INSTRUMENTATION BASES i

3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) 7 Injection pumps start and automatic valves positior, (2) Reactor trip, (3) feedwater isolation, (4) startup of the emergency diesel generators, (5) containment spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) turbine trip, (9) emergency feedwater pumps start and automatic valves position, i

(10) containment cooling fans start and automatic valves position, and (11) automatic service water valves position.

The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater below Setpoint, prevents the opening of the main valvesonT,TveswhichwereclosedbyaSafetyInjectionorHigh feedwater va Steam Generator Water Level signal, allows Safety Injection block l

so that components can be reset or tripped.

Reactor not tripped - prevents manual block of Safety Injection.

P-11 On increasing pressurizer pressure, P-11 automatically reinstates Safety Injection actuation on low pressurizer pressure. On decreasing pressure, P-ll allows the manual block of Safety-Injection actuation on low pressurizer pressure, and the manual block of SI and steamline isolation on steamline low pressure. On the manual block of steamline low pressure, manual block of

+

steamline low pressure automatically initiates steamline isolation on steam generator pressure negative rate - high.

P-14 On increasing steam generator water level, P-14 automatically trips the turbine and all feedwater isolation valves; inhibits feedwater control valve modulation; and blocks the start of the startup feed-l water pump.

3/4.3.3 MONITORING INSTRUMENTATION i

3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS l

The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:

(1) the associated action will be initiated when the 4

radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and determine whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents 4

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

INSTRUMENTATION BASES MONITORING 1NSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS (Continued) and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.

3/4.3.3.2 INCORE DETECTOR SYSTEM The OPERABILITY of the Incore Detector System ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core.

For the purpose of measuring F (Z) or F" a full incore flux map is used.

Quarter-core flux maps, as defined in WCAP-8d[8, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore detectors may be used for monitoring the QUADRANT l

POWER TILT RATIO when one Power Range channel is inoperable.

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capa-bility is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100.

The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earth-quakes," April 1974.

3/4.3.3.4 HETEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 REMOTE SHUTOOWN SYSTEM The OPERABILITY of the Remote Shutdown System ensures that sufficient capability is available to permit safe shutdown of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of Appendix A to 10 CFR Part 50.

SEABROOK - UNIT 1 B 3/4 3-4 Amendment No. 27

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,e POWER DISTRIBUTION LIMITS-t BASES i

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTHALPY RISE HOT i

CHANNEL FACTOR (Continued)

F"a will be maintained within its limits provided Conditions a, through

d. above are maintained. The relaxation of F"3 as a function of THERMAL POWER allows changes in the radial power shape for aTl permissible rod insertion limits.

Fuel rod bos.1 reduces the value of DNBR. Credit is available to offset this reduction in the generic margin. The generic margins, totaling 9.1% DNBR completely offset any rod bow penalties. This margin includes the following:

a.

Design limit DNBR of 1.30 vs. 1.28, I

b.

Grid spacing (K ) of 0.046 vs. 0.059, s

c.

Thermal diffusion coefficient of 0.038 vs. 0.059, y

d.

DNBR multiplier of 0.86 vs. 0.88, and e.

Pitch reduction.

The applicable values of rod bow penalties are referenced in the FSAR.

When an F measurement is taken, an allowance for both experimental errer

-l and manufacturi,ng tolerance must be made. An allowance of 5% is appropriate for a full-core map taken with the movable incore detectors, while 5.21% is appropriate for surveillance results determined with the fixed incore detectors. A 3% allowance is appropriate for manufacturing tolerance.

The Radial Peaking Factor, F, (Z), is measured periodically to provide assurance that the Hot Channel Fact,or, F,(Z), remains within its limit. The F,,

limit for RATED THERMAL POWER (F"[y) as provided in the CORE OPERATING LIMITS REPORT per Specification 6.8.1.6 was determined from expected power control maneuvers over the full range of burnup conditions in the core, j

When RCS F" is measured, no additional allowance:; are necessary grior to l

comparison with Me established limit. A measurement error of 4% for F when i

p determined with the movable incore detectors or 4.13% when determined with the fixed incore detectors has been allowed for in determination of the design DNBR value.

3/4.2.4 OUADRANT POWER TILT RATIO The purpose of this specification is to detect gross changes in core power distribution between monthly Incore Detector System surveillances.

l During normal operation the QUADRANT POWER TILT RATIO is set equal to zero once 4

acceptability of core peaking factors has been established by review of incore surveillances.

The limit of 1.02 is established as an indication that the l

power distribution has changed enough to warrant further investigation.

SEABROOK - UNIT 1 B 3/4 2-3 Amendment No. 27 e

f POWER DISTRIBUTION LIMITS BASES 3/4.2.5 DNB PARAMETERS t

The limits on the DNB-related parameters assure that each of the i

parameters is maintained within the normal steady-state envelope of operation I

assumed in the transient and accident analyses.

The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.

Operating procedures include allowances for measurement and indication uncertainty so that the limits of 594.3"F for T,, and 2205 psig for pressurizer are not exceeded.

j The measurement error of 2.4% for RCS total flow rate is based upon per-l forming a precision heat balance and using the result to normalize the RCS flow rate indicators.

Potential fouling of the feedwater venturi which might not be detected could bias the result from the precision heat balance in a noncon-servative manner. Therefore, a penalty of 0.1% for undetected fouling of the feedwater venturi is applied. Any fouling which might bias the RCS flow rate measurement greater than 0.1% can be detected by monitoring and trending vari-ous plant performance parameters.

If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load char.ges and other expected transient operation.

The periodic surveillance of indicated RCS flow is sufficient to detect i

only flow degradation which could lead to operation outside the specified i

limit.

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SEABROOK - UNIT I B 3/4 2-4 Amendment No. 9, 12 t

v t e Letter Sequence Request
TAC:M85020, (Approved, Closed)
Initiation Request, Request Acceptance... Administration Questions Answers Results Approval, Approval Other: ML20046C979, ML20056D703, ML20058B179, ML20059D213
MONTHYEAR1993-12-29 [Table View]

ML20059B029

Text

Attachment:

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