Text

Amends 99 & 63 to Licenses NPF-39 & NPF-85,respectively, Revising TS SR by Adding Optional Scram Insertion Time Test & TS SR for Control Rod Block & Source Range Monitoring Instrumentation
	ML20086Q366
Person / Time
Site:	Limerick
Issue date:	07/18/1995
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Philadelphia Electric Co
Shared Package
ML20086Q370	List: ML20086Q366; ML20086Q371;
References
	NPF-39-A-099, NPF-85-A-063 NUDOCS 9507280014
	Download: ML20086Q366 (20)
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UNITED STATES t

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NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 20066 4 001

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PHILADELPHIA ELECTRIC COMPANY DOCKET N0. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. NPF-39 1.

The Nuclear Regulatory Commission (the Com9ission) has found that:

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated August 22, 1994, as supplemented by letter dated July 3,1995, 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 i

Commission; i

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.

f f

9507280014 950719 PDR ADOCK 05000352 P

PDR

j

" 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-39 is hereby amended to read as follows:

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

99, are hereby incorporated into this license.

Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION pJohnF.Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 18, 1995

ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 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.

Remove Insert 3/4 1-6 3/4 1-6 3/4 2-9 3/4 2-9 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 3/4 3-88 3/4 3-88 3/4 9-4 3/4 9-4 8 3/4 1-2 B 3/4 1-2 i

a

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- REACTIVITY CONTROL SYSTEMS CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITINGbONDITLONFOROPERATION 3.1.3.2 Tae max < mum scram insertion time of each control rod from the fully withdrawn position to notch position 5, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed 7.0 seconds.

i APPLICABILITY: OPERATIONAL CONDITIONS I and 2.

ACTION:

a.

With the maximum scram insertion time of one or more control rods exceeding 7 seconds:

1.

Declare the control rod (s) with the slow insertion time inoperable, and 6

2.

Perform the Surveillance Requirements of Specification 4.1.3.2c.

at least once per 60 days when operation is continued with three or more control rods with maximum scram insertion times in excess of 7.0 seconds.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.1.3.2 The maximum scram insertion time of the control rods shall be demon-strated through measurement and, during single control rod scram time tests, the control rod drive pumps shall be isolated from the accumulators:

a.

For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER with reactor coolant pressure greater than or equal to 950 psig, following CORE ALTERATIONS or after a reactor shutdown that is greater than 120 days.

b.

For specifically affected individual control rods following maintenance on or modification to the control rod or control rod drive system which could affect the scram insertion time of those specific control rods in accordance with either "1" or "2" as follows:

l.a Specifically affected individual control rods shall be scram time tested at zero reactor coolant pressure and the scram insertion time from the fully withdrawn position to notch position 05 shall not exceed 2.0 seconds, and 1.b Specifically affected individual control rods shall be scram time tested at greater than or equal to 950 psig reactor coolant pressure prior to exceeding 40% of RATED THERMAL POWER.

2.

Specifically affected individual control rods shall be scram time tested at greater than or equal to 950 psig reactor coolant pressure.

c.

For at least 10% of the control rods, with reactor coolant pressure greater than or equal to 950 psig, on a rotating basis, and at least once per 120 days of POWER OPERATION.

LIMERICK - UNIT 1 3/4 1-6 Amendment No. 99

POWER DISTRIBUTION LIMITS

-LIMITING CONDITION FOR OPERATION (Continued)

ACTION a.

With the end-of-cycle recirculation pump trip system inoperable per Specification 3.3.4.2, operation may continue provided that, within I hour, MCPR is determined to be greater than or equal to the rated MCPR limit as a function of the average scram time (shown in the CORE OFERATING LIMITS REPORT) EOC-RPT inoperable curve, adjusted by the MCPR(P) and MCPR(F)

-factors as shown in the CORE OPERATING LIMITS REPORT.

b.

With MCPR less than the applicable MCPR limit adjusted by the MCPR(P) and MCPR(F) factors as shown in the CORE OPERATING LIMITS REPORT, initiate corrective action within 15 minutes and restore MCPR to within the required 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 25%

of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

c.

With the main turbine bypass system inoperable per Specification 3.7.8, operation may continue provided that, within I hour, MCPR is determined to be greater than or equal to the rated MCPR limit as a function of the average scram time (shown in the CORE OPERATING LIMITS REPORT) main turbine bypass valve inoperable curve, adjusted by the MCPR(P) and MCPR(F) factors as shown in the CORE OPERATING LIMITS REPORT.

EEY.E.lld$.EEEEl MR 4.2.3 NCPR, with:

1.0 prior to performance of the initial scram time measurements a.

t -

for the cycle in accordance with Specification 4.1.3.2a and during reactor startups prior to control rod scram time tests in accordance with Specification 4.1.3.2.b.l.b, or b.

t as defined in Specification 3.2.3 used to determine the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the conclusion of each scram time surveillance test required by Specification 4.1.3.2, shall be determined to be equal to or greater than the applicable MCPR limit, including application of the MCPR(P) and MCPR(F) factors as determined from tne CORE OPERATING LIMITS REPORT.

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and c.

Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating with a LIMITING CONTROL ROD PATTERN for MCPR.

d.

The provisions of Specification 4.0.4 are not applicable.

j i

Amendment No. 11.19,37,52,66,99 LIMERICK - UNIT 1 3/4 2-9

TABLE 4.3.6-1

'I CONTROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS

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CHANNEL OPERATIONAL-CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH g

TRIP FUNCTION CHECK TEST CALIBRATION")

SURVEILLANCE REQUIRED

x 1.

R00 BLOCK MONITOR n*

a.

Upscale N.A.

Q"'

R 1*

b.

Inoperative N.A.

Q")

N.A.

1*

c.

Downscale N.A.

Q")

R 1*

s 2.

APRM a.

Flow Biased Neutron Flux-Upscale N.A.

Q SA 1

b.

Inoperative N.A.

Q N.A.

1, 2, 5***

c.

Downscale N.A.

Q SA 1

d.

Neutron Flux - Upscale, Startup N.A.

Q SA 2, 5***

3.

SOURCE RANGE MONITORS t'

a.

Detector not full in N.A.

M""*), W")

N.A.

2, 5 b.

Upscale N.A.

M ""* ', W "'

R 2, 5 y

c.

Inoperative N.A.

M""*), W")

N.A.

2,~5 0

-d.

Downscale N.A.

M""*), W")

R 2, 5 4.

INTERMEDIATE RANGE MONITORS a.

Detector not full in N.A.

W

-N.A.

2, 5.

b.

Upscale N.A.

W R

2, 5 -

c.

Inoperative N.A.

W N.A.

2, 5

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d.

Downscale N..^..

W R

2, 5 5.

SCRAM DISCHARGE VOLUME

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a.

Water Level - High N.A.

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.R 1, 2, 5**

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REACTOR COOLANT SYSTEM RECIRCULATION FLOW

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h a.

Upscale N.A.

Q SA 1

y b.

Inoperative N.A.

Q N.A.

1 c.

Comparator N.A.

Q l'

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REACTOR MODE SWITCH SHUTDOWN POSITION N.A.

. R")

N.A.

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n q

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TABLE ' 4 ' 3.6-l'- (Centinued) ;

i CONTROL-ROD' BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS' m

's:

j

' TABLE NOTATIONS 0

l (a)~ Neutron-detectors may be excluded from CliANNEL CALIBRATION, (b) Deleted.

-(c) Includes. reactor manual control multipleting. system input.

For OPERATIONAL ~ CONDITION of Specification 13.1.4.3.

i

- With more than one control rod withdrawn.. Not applicable to control rods removed per _ Specification 3.9.10.1 or 3.9.10.2.

- - Required to be OPERABLE only prior to and during shutdown margin-demonstrations as performed per Specification 3.10.3.

-l f

(d) When in OPERATIONAL CONDITION 2.

(e) The provisions of Specification 4.0.4 are not applicable provided that the-i surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the IRNs are on Range 2 or below during a shutdown.

(f) When in OPERATIONAL CONDITION 5.

l (g) The provisions of Specification 4.0.4 are not applicable provided that the surveillance is performed within I hour r,fter the Reactor Mode Switch has been i

placed in the shutdown position.

i i

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'LINERICK - UNIT 1 3/4 3.-52 Amendment No. H, 66, 99

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= INSTRUMENTATION.

"'- - ' SOURCE RANGE MONITORS LIMITING CONDITION FOR OPERATION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE:

a.

In OPERATIONAL CONDITION 2*, three.

b.

In OPERATIONAL CONDITION 3 and 4, two.

APPLICABILITY:

OPERATIONAL CONDITIONS 2*, 3, and 4.

ACTION:

a.

In OPERATIONAL CONDITION 2* with one of the above required source range monitor channels inoperable, restore at least three source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source range monitor channels inoperable, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within I hour.

SURVEILLANCE RE0VIREMENTS 4.3.7.6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:

a.

Performance of a:

1.

CHANNEL CHECK at least once per:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in CONDITION.2*, AND b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in CONDITION 3 or 4.

2.

CHANNEL CALIBRATION ** at least once per 24 months.

b.

Performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days.

c.

Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 3.0 cps *** with the detector fully inserted.

With IRM's on range 2 or below.

- Neutron detectors may be excluded from CHANNEL CALIBRATION.

- - May be reduced, provided the source range monitor has an observed count rate and signal-to-noise ratio on or above the curve shown in Figure 3.3.6-1.

f LIMERICK - UNIT 1 3/4 3-88 Amendment No. 34, 71, 99

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1.,

ltEFUELING OPERATIONS m

b.,7 tSURVEILLANCE REQUIREMENTS (Continued)'

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b. '

Performance of a. CHANNEL FUNCTIONAL TEST at least once per 7 days.

l

~

c.

' Verifying. that the channel-count. rate is at least 3.0 cps:*

.i 4

1.

Prior to control rod withdrawal, 3

2.

Prior to and'at.least once per.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS, and i

3.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

Verifying,' within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to and at least'once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

.I during. that the RPS circuitry " shorting links" have been removed during:

-j 1.

The time any control rod is withdrawn,** or i

2.

Shutdown margin demonstrations.

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i 3

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q i

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. May be reduced, provided the source range monitor has an observed count rate.

l and signal-to-noise ratio on or above~ the curve shown in Figure 3.3.6-1.

j These channels are not required when sixteen or fewer fuel assemblies,-adja-cent to the SRMs, are in the core.

- Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

LIMERICK - UNIT 1 3/4 9-4 Amendment No. 4, 34, 99

'REACTlVITY CONTROL SYSTEMS BASES 3/4.1.3 CONTROL RODS The specification of this section ensure that (1) the minimum SHUTDOWN MARGIN is maintained, (2) the control rod insertion times are consistent with those used in the accident analysis, and (3) the potential effects of the rod drop accident are limited.

The ACTION statements permit variations from the basic requirements but at the same time impose more restrictive criteria for continued operation. A limitation on inoperable rods is set such that the resultant effect on total rod worth and scram shape will be kept to a minimum.

The requirements for the various scram time measurements ensure that any indication of systematic problems with rod drives will be investigated on a timely basis.

Damage within the control rod drive mechanism could be a generic problem, th:refore with a control rod immovable because of excessive friction or mechanical interference, operation of the reactor is limited to a time period which is reasonable to determine the cause of the inoperability and at the same time prevent operation with a large number of inoperable control rods.

Control rods that are inoperable for other reasons are permitted to be taken out of service provided that those in the nonfully-inserted position are consistent with the SHUTDOWN MARGIN requirements.

The number of control rods permitted to be inoperable could be more than the eight allowed by the specification, but the occurrence of eight inoperable rods could be indicative of a generic problem and the reactor must be shutdown for investigation and resolution of the problem.

The control rod system is designed to bring the reactor subcritical at a rate fast enough to prevent the MCPR from becoming less than the fuel cladding safety limit during the limiting power transient analyzed in Section 15.2 of the FSAR. This analysis shows that the negative reactivity rates resulting from the scram with the average response of all the drives as given in the specifi-cations, provided the required protection and MCPR remains greater than the fuel cladding safety limit.

The occurrence of scram times longer then those specified should be viewed as an indication of a systemic problem with the rod drives and therefore the surveillance interval is reduced in order to prevent operation of the reactor for long periods of time with a potentially serious problem.

Scram time testing at zero psig reactor coolant pressure is adequate to ensure that the control rod will perform its intended scram function during startup of the plant until scram time testing at 950 psig reactor coolant pressure is performed prior to exceeding 40% rated core thermal power.

The scram discharge volume is required to be OPERABLE so that it will be available when needed to accept discharge water from the control rods during a reactor scram and will isolate the reactor coolant system from the containment when required.

Control rods with inoperable accumulators are declared inoperable and Specification 3.1.3.1 then applies.

This prevents a pattern of inoperable accumulators that would result in less reactivity insertion on a scram than has been analyzed even though control rods with inoperable accumulators may still be inserted with normal drive water pressure. Operability of the accumulator ensures that there is a means available to insert the control rods even under the most unfavorable depressurization of the reactor.

LIMERICK - UNIT 1 B 3/4 1-2 Amendment No. 30, 99

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UNITED STATES '

NUCLEAR REGULATORY COMMISSION 5 -

I WAS)HNGTON, D.C. 20066-0001 -

PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. NPF-85 1.

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

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated August 22, 1994, as supplemented by letter dated July 3, 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; 1

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.

1 i

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-85 is hereby amended to read as follows:

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

63, are hereby incorporated into this license.

Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall J

be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMISSION k

Y l h b-John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 18,1995 i

i 1

A I

ATTACHMENT TO LICENSE AMENDMENT NO. 63 j

FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 1

1 Replace the following pages of the Appendix A Technical Specifications with I

the attached pages. The revised pages are identified by Amendment number and

{

contain vertical lines indicating the area of change.

i Remove Insert 1

3/4 1-6 3/4 1-6 i

3/4 2-9 3/4 2-9 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 i

3/4 3-88 3/4 3-88 3/4 9-4 3/4 9-4 8 3/4 1-2 8 3/4 1-2 j

I i

i

i

REACTIV.ITY CONTROL SYSTEMS JCONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion time of each control rod from the fully withdrawn position to notch position 5, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed 7.0 seconds.

APPLICABILITY: OPERATIONAL CONDITIONS I and 2.

ACTION:

a.

With the maximum scram insertion time of one or more control rods exceeding 7 seconds:

1.

Declare the control rod (s) with the slow insertion time inoperable, and 2.

Perform the Surveillance Requirements of Specification 4.1.3.2c.

at least once per 60 days when operation is continued with three or more control rods with maximum scram insertion times in excess of 7.0 seconds.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

The provisions of Specification 3.0.4 are not applicable.

SVRVElllANCE RE0UIREMENTS 4.1.3.2 The maximum scram insertion time of the control rods shall be demon-strated through measurement and, during single control rod scram time tests, the control rod drive pumps shall be isolated from the accumulators:

a.

For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER with reactor coolant pressure greater than or equal to 950 psig, following CORE ALTERATIONS or after a reactor shutdown that is greater than 120 days.

b.

For specifically affected individual control rods following maintenance on or modification to the control rod or control rod drive system which could affect the scram insertion time of those specific control rods in accordance with either "1" or "2" as follows:

1.a Specifically affected individual control rods shall be scram time tested at zero reactor coolant pressure and the scram insertion time from the fully withdrawn position to notch position 05 shall not exceed 2.0 seconds, and 1.b Specifically affected individual control rods shall be scram time tested at greater than or equal to 950 psig reactor coolant pressure prior to exceeding 40% of RATED THERMAL POWER.

2.

Specifically affected indivFual control rods shall be scram time tested at greater than or equal to 950 psig reactor coolant pressure.

c.

For at least 10% of the control rods, with reactor coolant pressure greater than or equal to 950 psig, on a rotating basis, and at least once per 120 days of POWER OPERATION.

LIMERICK - UNIT 2 3/4 1-6 Amendment No. 63 l

. POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

ACTION a.

With the end-of-cycle recirculation pump trip system inoperable per Specification 3.3.4.2, operation may continue provided that, within I hour, MCPR is determined to be greater than or equal to the rated MCPR limit as a function of the average scram time (shown in the CORE OPERATING LIMITS REPORT) E0C-RPT inoperable curve, adjusted by the MCPR(P) and MCPR(F) factors as shown in the CORE OPERATING LIMITS REPORT.

b.

With MCPR less than the applicable MCPR limit adjusted by the MCPR(P) and MCPR(F) factors as shown in the CORE OPERATING LIMITS REPORT, initiate corrective action within 15 minutes and restore MCPR to within the required 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 25% of RATED THERMAL i

POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

c.

With the main turbine bypass system inoperable per Specification 3.7.8, operation may continue provided that, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , MCPR is determined to be greater than or equal to the rated MCPR limit as a function of the average scram time (shown in the CORE OPERATING LIMITS REPORT) main turbine bypass valve inoperable curve, adjusted by the MCPR(P) and MCPR(F) factors as shown in the CORE OPERATING LIMITS REPORT.

{

SURVEILLANCE RE0VIREMENTS l

4.2.3 MCPR, with:

1.0 prior to performance of the initial scram time measurements a.

r =

for the cycle in accordance with Specification 4.1.3.2a and during i

reactor startups prior to control rod scram time tests in accordance with Specification 4.1.3.2.b.1.b, or i

b.

r as defined in Specification 3.2.3 used to determine the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the conclusion of each scram time surveillance test required by Specification 4.1.3.2, shall be determined to be equal to or greater than the applicable MCPR limit including application of the MCPR(P) and MCPR(F) factors as determined from the j

CORE OPERATING LIMITS REPORT.

l a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and c.

Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating with a LIMITING CONTROL R0D PATTERN for MCPR.

d.

The provisions of Specification 4.0.4 are not applicable.

i LIMERICK - UNIT 2 3/4 2-9 Anendment No. 4, 16, 48, 63

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TABLE 4.3.6 '. A7 4 4

' ".w.,

. CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTSi C

CHANNEL 0PERATIONAL i. i!i -

CHANNEL FUNCTIONAL CHANNEL

' ColN)ITIONS FOR W1ICHi

- '2

'5 TRIP FUNCTION '

CHECK TEST

_ CALIBRATION (*)

SURVEILLANCE REQUlRED

'A 1.

ROD BLOCK MONITOR a.

Upscale N.A.

.Q(*)

SA

'1 *

[ g:

b.

.Incperative N.A.

Q(*)

N.A.

1*

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c. - Downscale N.A.

Q SA 1*

w 2.

APRM a.

Flow Biased Neutron Flux-Upscale-N.A.

Q SA 1

.b.

Inoperative N.A.

Q N.A.

1, 2,: 5***

c.

Downscale N.A.

Q

-SA.

1-d.

Neutron Flux - Upscale, Startup N.A.

Q SA 2, 5***

3.

SOURCE RANGE-MONITORS 1

a.

Detector not full in N.A.

M(d)(*) W(f)

.N.A.

2, 5 -

l t' b.

Upscale N.A.

M(d)(*),W(f)

R 2, 5 c.

Inoperative N.A.

M(d)(*),W(f)

N.A.

2, 5.-

d.

Downscale N.A.

M(d)(*),W(f)

R 2,- 5 4.

INTERMEDIATE RANGE MONITORS

~

a.

Detector not full in N.A.

W N.A.

2, 5 b.

Upscale N.A.

W' R

2, 5 k-c.

Inoperative N.A.

W N.A.

2, 5 m

d. - Downscale N.A.

W' R

2, 5 k

g 5.

SCRAM DISCHARGE VOLUME

.E a.

Water Level - High N.A.

Q.

R 1,-2, 5**

6.

REACTOR COOLANT' SYSTEM RECIRCULATION FLOW 4

'a.

Upscale -

N.A.

-Q' 3A-1 g

b.

Inoperative N.A..

Q N.A.

1 c.

Comparator N. A.'

Q SA 1

O 7.

REACTOR MODE SWITCH SHUTDOWN POSITION N.A.

R(8I N.A.

.i, i4 -

3

. -.... =..

= -..... -......

TABLE 4.3.6-1-(Continued)

CONTROL R0D BLOCK INSTRUMENTATION SVRVEILLANCE RE0VIREMENTS TABLE NOTATIOM (a)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b)

Deleted.

l (c)

Includes. reactor manual control multiplexing system input.

For OPERATIONAL' CONDITION of Specification 3.1.4.3.

With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

Required to be OPERABLE only prior to and during shutdown margin deronstrations as performed per Specification 3.10.3.

(d)

Whan in OPERATIONAL CONDITION 2.

(e)

The provisions of Sp_ecification 4.0.4 are not applicable provided that the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the IRMs are on Range 2 or below during a shutdown.

(f)

When in OPERATIONAL CONDITION 5.

(g)

The provisions of Specification 4.0.4 are not applicable provided that the surveillance is performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the Reactor Mode Switch has been placed in the shutdown position.

LIMERICK - UNIT 2 3/4 3-62 Amendment No. 7, 48, 63

.IhSTRUMENTATION SOURCE RANGE MONITQRS LIMITING' CONDITION FOR OPERATION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE:

I

a. In OPERATIONAL CONDITION 2*, three.

b. In OPERATIONAL CONDITION 3 and 4, two.

APPLICABILITY:

OPERATIONAL CONDITIONS 2*#, 3, and 4.

ACTION:

a. In OPERATIONAL CONDITION 2* with one of the above required source range monitor channels inoperable, restore at least three source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

b. In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source range monitor channels inoperable, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within I hour.

SURVEILLANCE RE0VIREMENTS 4.3.7.6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:

a.

Performance of a:

1.

CHANNEL CHECK at least once per:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in CONDITION 2*,

and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in CONDITION 3 or 4.

2.

CHANNEL CALIBRATION ** at least once per 24 months.

l b.

Performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days.

I l

c.

Verifying, prior to withdrawal of control rods, that the SRM count I

rate is at least 3.0 cps *** with the detector fully inserted.#

With IRM's on range 2 or below.

- Neutron detectors may be excluded from CHANNEL CALIBRATION.

i

- - May be reduced, prr,vided the source range monitor has an observed count rate l

and signal-to-noist ratio on or above the curve shown in Figure 3.3.6-1.

During initial startup test program, SRM detectors may be partially i

withdrawn prior to IRM on-scale indication provided that the SRM channels l

remain on scale above 100 cps and respond to changes in the neutron flux.

LIMERICK - UNIT 2 3/4 3-88 Amendment No. 3, 34, 63 N

fl 7

, REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) b.

Performance of a CHANNEL FUNCTIONAL TEST at least once per 7 days.

c.

Verifying that the channel cc: ant rate is at least 3.0 cps:*

-1.

Prior to control rod withdrawal, 2.

Prior to and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS.

and 3.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

Verifying, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during, that the RPS circu3try " shorting links" have been removed during:

1.

The time any control rod is withdrawn,** or 2.

Shutdown margin demonstrations.

t i

J 1

May be reduced, provided the source range monitor has an observed count rate and signal-to-noise ratio on or above the curve shown in Figure 3.3.6-1.

These channels are not required when sixteen or fewer fuel assemblies,.

adjacent to the SRMs, are in the core.

- Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

1 i

i

-)

l i

LIMERICK - UNIT 2 3/4 9-4 Amendment No. 3, 63

BEACTIVITV CONTROL SYSTFMJ s

l BASES 3/4.1.3 CONTROL RODS l

The specification of this section ensure that (1) the minimum SHUTDOWN MARGIN is maintained, (2) the control rod insertion times are consistent with l

those used in the accident analysis, and (3) the potential effects of the rod drop accident are limited.

The ACTION statements permit variations from the basic j

requirements but at the same time impose more restrictive criteria for continued

~

operation. A limitation on inoperable rods is set such that the resultant effect on total rod worth and scram shape will be kept to a minimum. The requirements for the various scram time measurements ensure that any indication of systematic problems with rod drives will be investigated on a timely basis.

Damage within the control rod drive mechanism could be a generic problem, therefore with a control rod immovable because of excessive friction or mechanical interference, operation of the reactor is limited to a time period which is reasonable to determine the cause of the inoperability and at the same time prevent operation with a large number of inoperable control rods.

Control rods that are inoperable for other reasons are permitted to be taken out of service provided that those ir, the nonfully-inserted position are consistent with the SHUTOOWN MARGIN requirements.

The number of control rods permitted to be inoperable could be more than the eight allowed by the specification, but the occurrence of eight inoperable rods could be indicative of a generic problem and the reactor must be shutdown for investigation and resolution of the problem.

The control rod system is designed to bring the reactor subcritical at a rate fast enough to prevent the MCPR from becoming less than the fuel cladding safety limit during the limiting power transient analyzed in Section 15.2 of the FSAR.

This analysis shows that the negative reactivity rates resulting from the scram with the average response of all the drives as given in the specifications, provided the required protection and MCPR remains greater than the fuel cladding safety limit. The occurrence of scram times longer then those specified should be viewed as an indication of a systemic problem with the rod drives and therefore the surveillance interval is reduced in order to prevent operation of the reactor for long periods of time with a potentially serious problem.

Scram time testing at zero psig reactor coolant pressure is adequate to ensure that the control rod will perform its intended scram function during startup of the plant until scram time testing at 950 psig rector coolant pressure is performed prior to exceeding 40% rated core thermal powee.

The scram discharge volume is required to be OPERABLE so that it will be available when needed to accept discharge water from the control rods during a reactor scram and will isolate the reactor coolant system from the containment l

when required.

Control rods with inoperable accumulators are declared inoperable and Specification 3.1.3.1 then applies. This prevents a pattern of inoperable accumulators that would result in less reactivity insertion on a scram than has been analyzed even though control rods with inoperable accumulators may

'i still be inserted with normal drive water pressure. Operability of the accumulator ensures that there is a means available to insert the control rods even under the most unfavorable depressurization of the reactor.

LIMERICK - UNIT 2 B 3/4 1-2 Amendment No. 63

_

ML20086Q366

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