Text

Amend 151 to License DPR-53,allowing Operation of Unit 1 W/Ctr Control Element Assembly Excluded from Tech Spec Requirements for Operability & Alignment for Remainder of Operating Cycle 10
	ML20066J166
Person / Time
Site:	Calvert Cliffs
Issue date:	02/20/1991
From:	Greenman E; Office of Nuclear Reactor Regulation
To:	;
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ML20066J168	List: ML20066J166; ML20066J171;
References
	NUDOCS 9102260010
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j NUCLEAR REGULATORY COMMISSION g

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i BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 l

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO FACILITY CPERATING LICENSE i

Amendment No. 151 L

License No. DPR-53 L

1.

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

A.

The application for amennment by Baltimore Gas and Electric Company (the licensce) dated February 8, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulatons 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 (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:

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.

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. DPR-53 is herEby amended to read as follows:

9102260010 910220 PDR ADOCK 05000317 P

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.151, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented upon receipt.

FOR THE NUCLEAR REGULATORY COMMISSION

& k-Edward G. Greenman, Acting Assistant Director for Region ! Reactors Division of Reactor Projects - I/II l

Office of Nuclear Reactor Regulation l

Attachment.

Changes to the Technical Specifications Date of Issuance:

February 20, 1991 1

i i

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ATTACHMENT TO LICENSE AMENDHENT AMEN 0 MENT NO.151 FACILITY OPERATING LICENSE NO. OPR-53 DOCKET 110. 50-317 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 1-1 3/4 1-1 3/4 1-2*

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I 3/4.1 REACTIVITY CONIROL_ShlfMS 3/4.1.1 _B0 RATION CONTROL 0

SHUTDOWN MARGIN - T

> 200 F avo LINITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MRGIN shall be equal to or greater than the limit line of Figure 3.1-lb.

APPLICABIllTY:- MODES 1, 2**, 3, and 4.

ACTION:

With the SHUTDOWN MRGIN less than the limit ilne of Figure 3.1-lb immediately initiate and continue boration at 2 40 gpm of 2300 ppm boric acid solution or equivalent until the required SHUTDOWN MRCIN is restored.

SURVEILLANCE REQWRENENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be equal to or greater than the limit of Figure 3.1-lb:

Within one hour after detection of an inoperable CEA(s)+ and at a.

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the CEA(s)+ is inoperable.

If the inoperable CEA is immovable or untrippable, the above required SHUTDOWN MRGIN shall be increased by an amount at least equal o the withdrawn worth of the immovable or untrippable CEA(s) b.

When in MODES 1 or 2, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that CEA group withdrawal + is within the Transient insertion l

Limits of Specification 3.1.3.6.

c.

When in MODE 2##, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor criticality by verifying that the predicted critical CEA position + is within the limits of Specification 3.1.3.6.

l d.

Prior to initial operation above 5% RATED WRML POWER after each fuel loading, by consideration of the factors of e below, with the CEA groups at the Transient Insertion Limits of l

Specification 3.1.3.6.

Adherence to Technical Specification 3.1.3.6 as specified in Surveillance Requirements 4.1.1.1.1 assures that there is sufficient available shutdown margin to match the shutdown margin requirements of the safety analyses.

See Special Test Exception 3.10.1.

With Keff 1 1.0 With K ff 1.0 ExcludTng<thecenterCEAduringCycle10.

l

+

CALVERT CLIFFS - VNIT 1 3/4 1-1 Amendment No.-21/52//E////EE/

19$/J)p,151

~

. REACTIVITY CONTROL SYSTEMS ElayEILLANCE REQUIREMENTS (Continued) e.

When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1.

Reactor coolant system boron concentration, 2.

CEA position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within 1.0% A k/k at least once per 31 Effective Full Power Days (EFPD).

This ccmparison shall consider at least those factors stated in Specification 4.1.1.1.1.e, above.

The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions arior to exceeding a fuel burnup of 60 Effective Full Power Days after eac1 fuel loading.

CALVERT CLIFFS - UNIT 1 3/4 1-2

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o (87%) NIDWYW NMOO10HS CALVDLT CLIFTS - UNIT 1 3/4 1 2a Amendment No.130

l RFACTIVITY CONTROL.;YSTEMS 0

SHUTDOWN MRGIN - T 1 200 F avg LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MRGIN shall be 2 3 0% A k/k.

APPLICABILITY: MODE 5 a.

Pressurizer level 2 90 inches from bottom of the pressurizer, b.

Pressurizer level < 90 inches from bottom of the pressurizer and all sources of non-borated water s 88 gpm.

ACILQH:

a.

With the SHUTDOWN MRGIN < 3.0% A k/k, immediately initiate and continue boration at 2 40 gpm of 2300 ppm boric acid solution or erluivalent until the required SHUTDOWN MRGIN is restored.

b.

With the pressurizer drained to 1 90 inches and all sources of non-borated water > 88 gpm, immediately suspend all operations involving positive reactivity change > while the SHUTDOWN M RGIN is increased to compensate for the additional sources of non borated water or reduce the sources of non borated water to 1 88 gpm.

EURYEILLANCI_REQUIRlMENTS 4.1.1.2 The SHUTDOWN MRGIN shall be determined to be 2 3.0% A k/k:

a.

Within one hour after detection of an inoperable CEA(s)+ and at liast once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the CEA(s)+ is inoperable.

If the inoperable CEA+ is immovable or untrippable, the above required SHUTDOWN MRGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA(s)+.

l b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1.

Reactor coolant system boron concentration, 2.

CEA position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross therma' energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.2.2 With the pressurizer drained to S 90 inches determine:

a.

Within one hour and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter that the level in the reactor coolant system is above the bottom of the hot leg nozzles, and b.

Within one hour and esery 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter that the sources of non-borated water are 188 gpm or the shutdown margin has compensated for the additional sources.

+

Excluding the center CEA during Cycle 10.

CALVERT CLIFFS - UNIT 1 3./4 1-3 Amendment No. ##E,151

REACTIVITY CONTROL SYSTEMS 3.4.1.3 MOVABLE CONTROL ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.1.3.1 The CEA Motion Inhibit and all shutdown and regulating CEAs+

l shall be OPERABLE with each CEA of a given group positioned within 7.5 inches (indicated position) of all other CEAs in its group.

APPLICABILITY: MODES 1* and 2*

ACTION:

3 s

With one or more CEAs* inoperable due to being immovable as a l

a.

result of excessive friction or mechanical interference or known to be untrippable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

t b.

With the CEA Motion inhibit inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

1.

Restore the CEA Motion Inhibit to OPERABLE status, or-l 2.

Place and maintain the CEA drive system mode switch in l

either the "Off" or any " Manual Mode" position and fully withdraw all CEAs in groups 3 and 4 and withdraw the CEAs+

in group 5 to less than 5% insertion, or 3.

Be in at least HOT STANDBY.

i c.

With one CEA inoperable + due to c.uses other than addressed by ACTION a, above, and inserted beyond the Long Term Steady State Insertion Limits but within its above specified alignment requirements, operation in MODES 1 and 2 may continue for up to 7 days per occurrence with a total accumulated time of s 14 days per calendar year, d.

With one CEA inoperable + due to causes other than addressed by ACTION a, above, but within its above specified alignment requirements and either fully withdrawn or within the Long Term Steady State Insertion Limits if in CEA group 5, operation in MODES 1 and 2 may continue.

t See Special Test Exceptions 3.10.2 and 3.10.4.

+

Excluding the center CEA during Cycle 10.

CALVERT CLIFFS - UNIT 1 3/4 1-17 Amendment No. J/7, 151

REACTIVITY CONTROL SYSTEMS UMITING CONDITION FOR OPERATION With one or more CEA.,' misaligned from any other CEAs in its l

e.

group by more th.n 7.5 inches but less than 15 inches, operation in PSOES I and 2 may continue, provided that within one hour the misaligned CEA(s) is either:

1.

Restored to OPERABLE status within its above specified alignment requirements, or 2.

Declared inoperable. After declaring the CEA+ inoperable l

operation in MODES 1 and 2 may continue for up to 7 days per occurrence with a total accumulated time of 114 days per calendar year provided all of the following conditions are met:

The THERMAL POWER level shall be reduced to 170Y. of a.

the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combir tion within one hour; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used, p.

Within one hour after reducing the THERMAL POWER as required by a) above, the remainder of the CEAs+ in thegroupwiththeinoperableCEA+shallbgaligned to within 7.5 inches of the inoperable CEA while maintaining the allowable CEA sequence and intertion limits shown on Figure 3.1-2; the THERMAL POWLR level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

f.

With one CEA+ misaligned from any other CEA+ in its group by l

15 inches or more, operation in MF, I and 2 may continue, provided that the misaligned CEA+ is positioned within 7.5 inches of the other CEAs+ in its group in accordance with the time allowance shown in Figure 3.1-3.

The pre-misaligned Ffvalueusedtodeterminetheallowabletimetorealignthe CEA+ from Figure 3.1-3 shall be the latest measurement taken l

within 5 days prior to the CEA misalignment.

If no measurements were taken within 5 days prior to the misalignment, a pre misaligned Ff of 1.65 shall be assumed.

g.

With one CEA+ misaligned from any other CEA+ in its group by 15 inches or more at the conclusion of the time allowance permitted in Figure 3.1-3, immediately start to implement the following actions:

1.

If the THERMAL POWER level prior to the misalignment was greater than 507. of RATED THERMAL POWER, THERMAL POWER shall be reduced to less than the greater of:

Excluding the center CEA during Cycle 10.

+

/

CALVERT CLIFFS - UNIT 1 3/4 1-18 Amendment No. J27, 151

BEACTIVITY CONTROL SYSTEMS LIMlllMG CONDITION FOR OPERATION a)

-50% of RATED YHERMAL POWER b) 75% of the THERMAL POWER level prior to the miralignment within one hour after exceeding the time allowance permitted by Figure 3.1-3.

2.

If the THERMAL POWER level prior to the misalignment was s 50%

of RATED THERMAL POWER, maintain THERMAL POWER no higher than the value prior to the misalignment.

If negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used. Within one hour after establishing the appropriate THERMAL POWER as required above, either:

1.

Restore the CEA+ to within the above specified alignment l

requirements, or 2.

Declare the CEA+ inoperable. After declaring the CEA inoperable, POWER OPERATION may continue for up to 7 days per occurrence with a total accumulated time of s 14 calendar year provided the remainder of the CEAs+ days per in the group l

with the inoperable CEA are aligned to within 7.5 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, h.

With more than one CEA+ inoperable or misaligned from any other CEA in its group by 15 inches (indicated posttion) or more, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1.

For the purposes of performing the CEA+ operability test of TS 4.1.3.1.2, if the CEA has an inoperable position indication channel, the alternate indication system (pulse counter or voltage dividing network) will be used to monitor position.

If a direct position indication (full out reed switch or voltage dividing r.etwork) cannot be restored within ten minutes from the commencement of CEA motion, or CEA withdrawal exceeds the surveillance testing insertion by > 7.5 inches, the position of the CEA shall be assumed to have been > 15 inches from its group at the commencement of CEA motion.

+

Excluding the center CEA during Cycle 10.

CALVERT CLIFFS - UNIT 1 3/4 1-19 Amendment No. 2E/EhJJ7,151

REACTIVITY CONTROL SYSTEMS HRVEILLANCE REDE R@ENTS 4.1.3.1.1 The position of each CEA+ shall be determined to be within 7.5 inches (indicated position) of all other CEAs in its group 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 Deviation Circuit and/or CEA Motion Inhibit are inoperable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.

f ach CEA+ not fully inserted shall be determined to be OPERABa t., inserting it at least 7.5 inches at least once per 31 days.

4.1.3.1.3 The CEA Motion Inhibit shall be demonstrated OPERABLE at least once per 31 days by a functional test which verifies that the circuit

-maintains the CEA group overlap and sequencing requirements of

pecification 3.1.3.6 and that the circuit also prevents any CEA from being misaligned from all other CEAs in its group by more than 7.5 inches (indicated position).+

+

Excluding the center CEA during Lycle 10.

I CALVERT CLIFFS - UNIT 1 3/4 1-19A Amendment No. J27, 151

REACTIVITY CONTROL SYSTEMS 4

4 POSITION INDICATOR CHANNELS UNITING CONDITION FOR OPERATION 3.1.3.3 At least two of the following three CEA position indicator i

channels shall be OPERABLE for each shutdown and regulating CEA+:

I CEA voltage divider reed switch position indicator channel, a.

capable of determining the absolute CEA position within 1.75 inches; b.

CEA " Full Out" or " Full In" reed switch position indicator channel, only if the CEA is fully withdrawn or fully inserted, as verified by actuation of the applicable position indicator:

and c.

CEA pulse counting position indicator channel.

APPLICABILITY:

MODES 1 and 2.

ACTION:

With a maximum of one CEA+ per group having its voltage divider a.

reed switch position indicator channel or its pulse counting position indicator channel inoperable and the CEA(s) with the inoperable position indicator channel partially inserted, either:

1.

Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months a)

Restore the inoperable position indicator channel to OPERABLE status, or b)

Be in at least HOT STANDBY, or c)

Reduce THERMAL PCWER to 1 70% of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used.

Operation at or below this reduced THERMAL POWER level may continue provided that within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

1)

The CEA group (s)+ with the inoperable position indicator is fully withdrawn while maintaining the withdrawal sequence required by Specification 3.1.3.6 and when this CEA group re v.hes its fully withdrawn position, the " Full Out" limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully withdrawn.

Subsequent to fully withdrawing this CEA group (s), the THERMAL POWER level may be returned to a level consistent with all other applicable specifications and operation may continue per Specification 3.1.3.3 above; or 2)

The CEA group (s)+ with the inoperable position l

indicator is fully inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THERMAL POWER level required by Specification 3.1.3.6 and when this CEA group reaches its fully

+

Excluding the center CEA during Cycle 10.

)

CALVERT CLIFFS - UNIT 1 3/4 1-21 AmendmentNo.12/7J/E//99/

JEE,'151

l REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPEB&I1ON inserted position, the " Full In" limit of the CEA with the inoperable indicator is actuated and verifies this CEA to be fully inserted.

Subsequent operation shall be within the limits of Specification 3.1.3.6, and may continue per Specification 3.1.3.3 above.

2.

or, if the failure existed before entry into MODE 2 or groups (s)}ortoan"allCEAsout" configuration,theCEA occurs pr with inoparable position indicator channel must be moved to the " Full Out" position and verified to be fully withdrawn via a " Full Out" indicator.

These actions must be completed within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of entry into MODE 2 and prior to exceeding 70% of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.

The provisions of Specification 3,0.4 are not applicable. Once these actions are completed, operation may continue per Specification 3.1.3.3 above.

b.

With more than one CEA+ per group having its CEA pulse counting l

position indicator channel and either (1) the " Full Out" or

" Full In" position indicator, or (2) the voltage divider position indicator channel inoperable, operation in MODES 1 and 2 may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided that for the affected CEAs, either:

1.

The CEA voltage divider reed switch position indicator channels are OPERABLE, or 2.

The CEA " Full Out" or " Full In" reed switch position indicator channels are OPERABLE, with the CEA fully withdrawn or fully inserted as verified by actuation of the applicable position indicator.

SURVEILLANCE REQLLIREMENTS 4.1.3.3.1 Each required CEA+ position indication channel shall be l

determined to be OPERABLE by determining CEA positions as follows at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , by:

a.

Verifying the CEA pulse counting position indicator channels and the CEA voltage divider reed switch position indicator channels agree within 4.5 inches, or b.

Verifying the CEA pulse counting position indicator channels-and the CEA " Full Out" or " Full In" reed switch position indicator channels agree within 4.5 inches, or c.

Ver!fying the CEA voltage divider reed switch position indicator channels and the CEA " Full Out" or " Full In" reed switch position indicator channels agree within 4.5 inches.

4.1.3.3.2 During time intervals when the deviation circuit is inoperable, the above verification of required CEA+ position indicator l

channels shall be made at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

+

Excluding the center CEA during Cycle 10.

CALVERT CLIFFS - UNIT 1 3/4 1-22 Amendment No. EE// h E MSE, 151

REAC11VITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDIT10E FOR OPEBATION 3.1.3.4 The individual full length (shutdown and control) CEA+ drop time, from a fully withdrawn position, shall be < 3.1 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:

0 a.

T 2 515 F, and avg b.

All reactor coolant pumps operating.

APPLICABillTY: MODES 1 and 2.

ACTION:

a.

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

b.

With the CEA drop times within limits but determined at less l

than full reactor coolant flow, operation may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable for the reactor coolant pump combination operating at the time of CEA drop time determination.

EURVEILLAN.fE RE0l!JRWEN15 4.1.3.4 The CEA drop time of full length CEAs+ shall be demonstrated through measurement prior to reactor criticality:

For all CEAs following each removal of the r', actor vessel head, a.

b.

For specifically affected individual (W. following any maintenance on or modification to the tiA drive system which could affect the drop time of those specific CEAs, and c.

At least once per refueling interval.

Excluding the center CEA during Cycle 10.

+

CALYERT CLIFFS UNIT 1 3/4 1-23 Amendment No. J2/J h EE/129, 151

~

REACTIVITY CONTROL SYST[tti SBl1TDOWN CEA INSERTION _ LIMIT LIMITING CONDITION FQllfPERATION 3.1.3.5 All shutdown CEAs shall be withdrawn to at least 129.0 inches.

APPLICABILITY: MODES 1 and 2*#,

ACTION:

With a maximum of one shutdown CEA withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, to less than 129.0 inches, within one hour oither:

a.

Withdraw the CEA to at least 129.0 inches, or b.

Declare the CEA Inoperable and apply Specification 3.1.3.1.

SERVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown CEA shall be determined to be withdrawn to at least 129.0 inches:

a.

Within 15 minutes prior to withdrawal of any CEAs+ in regulating groups 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.

See Special Test Exception 3.10.2.

With Keffl 1.0

+

Excluding ti.a center CEA during Cycle 10.

l l

CALVERT CLIFFS - UNIT 1 3/4 1-24 Amendment No. 4,151

REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMll)

LIMITING CONDITION FOR OPERATION 3.1.3.6 The regulating CEA+ groups shall be limited to the withdrawal sequence and to the insertion limits shown on Figure 3.1 2 (regulating CEAs are considered to be fully withdrawn in accordance with Figure 3.12 when withdrawn to at least 129.0 inches) with CEA insertion between the Long Term Steady State Insertion Limits and the Transient insertion Limits restricted to:

a.

1 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval, b.

1 5 Effective Full Power Days per 30 Effective Full Power Day interval, and c.

s 14 Effective full Power Days per calendar year.

APPLICABILITY: MODES 1* and 2*#.

ACTION:

a.

With the regulating CEA+ groups srted beyond the Transient l

Insertion Limits, except for suaeillance testing pursuant to Specification 4.l.S.I.2, within two hours 01ther:

1.

Restore the regulating CEA groups to within the limits, or 2.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the CEA group position using Figure 3.1-2.

b.

With the regulating CEA+ groups inserted between the Long Term Steady State Insertion Limits and the Transient insertion Limits for intervals > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval, except during operations pursuant to the provisions of ACTION items c.

and e. of Specification 3.1.3.1, operation may proceed provided either:

1.

The Short Term Steady State Insertion Limits of Figure 3.1-2 are not exceeded, or 2.

Any subsequent increase in THERMAL POWER is restricted to 5 5% of RATED THERMAL POWER per hour.

See Special Test Exceptions 3.10.2 and 3.10.4.

f With Kpfp 1.0.

+

The center CEA may be excluded from the determination of Bank 5 position during Cycle 1).

CALVERT CLIFFS - UNIT 1 3/4 1-25 Amendment No. JE/rgg,151

REACTIVITY CONTROL SYSTEMS LIMITING CONQ1110N FOR OPERAT10lLLConlittugd)

With the regulating CEA+ groups inserted between the Long Term c.

Steady State Insertion Limits and the Transient Insertion Limits for intervals > 5 EFPD per 30 f.FPD interval or > 14 EFPD per calendar year, except during operaricas pursuant to the provisions of ACTION items c. and e. of Specification 3.1.3.1, either:

1.

Restore the regulating sroups to within the Lon Steady State Insertion Limits within two hours,g Term or 2.

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

.51tRY_EILLANCE RE0hEBilill_.

4.1.3.6 The position of each regulating CEA+ group shall be determined l

to be within the Transient 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 PDIL Alarm Circuit is inoperable, then verify-the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

The accumulated times during which the regulating CEA groups are inserted beyond the Steady State Insertion Limits but within the Transient Insertion Limits shall be determined at least once Per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

+

The center CCA may be excluded from the determination of Bank 5 position during Cycle 10.

i i

l l

l CALVERT CLIFFS - UNIT 1 3/4 1-26 Amendment No.151-

l 3/4.2 POWER DISTRIBUTION LINITS LINEAR HEAT RATE LINITING CONDITION FOR OPERATION 3.2.1 The linear heat rate shall not exceed the limits shown on Figure 3.2-1.

APPLICABILITY:

MODE 1.

ACTION:

With the linear heat rate exceeding its limits, as indicated by four or more coincident ince e channels or by the AXIAL SilAPE INDEX outside of the power dependen'..:ontrol limits of Figure 3.2 2, within 15 minutes initiate corrective action to reduce the linear heat rate to within the limits and either:

a.

Restore the linear heat rate to within its limits within one hour, or b.

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

EURVEILLANCE REWlRQ1ENTS 4.2.1.1 The provisions-of Specification 4.0.4 are not applicable.

4.2.1.2 The linear heat rate shall be determined to be within its limits I

by continuously monitoring the core power distribution with either the excore detector monitoring system or with the incore detector monitoring i

system.

4.2.1.3 Excore Detestor Monitorina System - The excore detector monitoring system may be used for monitoring the core power distribution by:

a.

Verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that the full length CEAs+

are withdrawn to and maintained at or beyond the Long Term Steady State Insertion Limit of Specification 3.1.3.6.

i b.

Verifying at least once per 31 days that the AXIAL SHAPE INDEX alarm setroints are adjusted to within the limits shown on Figure 3.2-2.

+

Excluding the center CEA during Cycle 10.

CALVERT CLIFF.C - UNIT 1 3/4 2-1 Amendment No. E U JJ,151

1 l

POWER DISTRIBUTION LIMITS TOTALPLANARRADIALPEAKINGFACTOR-F}y LIMITING CONDITION FOR OPJRATION The calculated value of F}y, defined as F}y F

3.2.2.1 xy(1+T ), shall q

be limit 2d to s 1.70.

APPLICABIljJJ: MODE 1*.

ACTION:

WithF[y>1.70,within6hourseither:

a.

Reduce THERMAL POWER to bring the combination of THERMAL POWER andF[y to within the limits of Figure 3.2-3a and withdraw the full length CEAs+ to or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or b.

Be in at least HOT STANDBY.

SVRVEILLANCE RQWRMEES_

4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.

F}y shall be calculated by the expression F[y Fxy(1+T ) and 4.2.2.1.2 q

F}y shall be determined to be within its limit at the following intervals:

a.

Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading, b.

At least once per 31 days of accumul

d operation in MODE 1, and c.

Within four hours if the AZIMUTHAL POWER TILT (T ) is > 0.030.

q

)

See Special Test Exception 3.10.2.

+

Excluding the center CEA during Cycle 10.

CALVERT CLIFFS - UNIT 1 3/4 2-6 Amendment No. JJ/JJ/ #//J/ S,

151 l

POWER DISTRIBUTION LIMITS SURVEILLANCE REQQ1REMEHIL[C.gntinued) shallbedeterminedeachtimeacalculationofF[y 4.2.2.1.3 F

is xy required by using the incore detectors to obtain a power distribution map with all full length CEAs+ at or above the long Term Steady State Insertion Limit for the existing Reactor Co01 ant Pump combination.

This determination shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects.

shall be determined each time a calculation of F}y 4.2.2.1.4 T

is q

required and the value T usedtodetermineF}y shall be the measured q

value of T.

q v

h

+

Excluding the center CEA during Cycle 10.

CALVERT CLIFFS - UNIT 1 3/4 2 7 Amendment Ns. 21/J2/7J, 151 I

j$MQLQLSTRIBUTION tIMITS TOTALPLANARRADIALPEAKINGFACTOR-F}y l.1MillRGJLMRLUEl02 OPERA _ TION 3.2.2.2 The value of N presently used in Specification 4.2.1.3 shall be in accortlance with Figure 3.;-3b.

APPLICABILITY:.400E 1 when operating in a:cordance with Specification 4.2.1.3.

KUQN:

With the value of N presently used in Specification 4.2.1.3 exceeding the limit shown in Figure 3.2 3b, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a.

Reduce the value of N used in Specification 4.2.1.3 to within the limits of Figure 3.2 Sb; or b.

Be in at least fl0T STANDBY.

SURVEI1 LANCE REQUIREMENTS 4.2.2.2.1 The provisions of Specification 4.0.4 are not applicable.

F[y shallbecalculatedbytheexpressionF}y-F (1+T ) and 4.2.2.2.2 q

N shall be determined to be within its limit by monitoring F at the xy following intervals:

a.

Prior to operation above 70 percent of RATED THERMAL POWER after each fuel inading, b.

At least once per 3 days of accumulated operation in MODE 1, shall be determined each time a calculation of F[y 4.2.2.3 F is xy required by using the incore detectors to obtain a oower distribution map with all full length CEAs+ at or above the Long Term Steady State Insertion Limit for the existing Reactor Conlant Pump combination.

This determination shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects.

shall be determined each time a calculation of F}y 4.2.2.2.4 T

is q

required and the value of T usedtodetermineF}y shall be the measured q

value of T.

q

+

Excluding the center CEA during Cycle 10.

1 CALVERT CLIFFS - UNIT 1 3/4 2-8 Amendment No. /J, 151

IM fjLQ1STRIBUTION LINITS TOTALINTEGRATEDRADIALPEAKINGFACTOR-Ff LIMITING CONDITION FQR OPERATIM The calculated value of Ff, defined as Ff - F (1+T ), shall be 3.2.3 r

q limited to 1 1.650.

APPLICABILITY: MODE 1*.

ACTION:

WithFf>1.650within6hourseither:

a.

Be in at least HOT STANDBY, or b.

Reduce THERMAL POWER to bring the combination of THERMAL POWER andFftowithinthelimitsofFigure3.2.3c,withdrawthefull I

length CEAs+ to or beyond the Long Term Steady State Limits of Specification 3.1.3.6, and insert new value of Ff in BASSS; or c.

Reduce THERMAL POWER to bring the combination of THERMAL POWER andFftowithinthelimitsofFigure3.2-3candwithdrawthe 4

full length CEAs to or beyond the long Term Steady state Insertion Limits of Specification 3.1.3.6.

The THERMAL POWER limit determined from Figure 3.2-3c shall then be used to establish a revised upper THERMAL POWER level limit on 4

Figure 3.2-4 (truncate Figure 3.2-4 at the allowable fraction of RATED THERMAL POWER det, mined by Figure 3.2-3c) and subsequent operation shall be maintained within the reduced acceptable operation region of Figure 3.2-4.

SEVEILLANCE RE0VIRENENTS 4.2.3.1 The provision of Specification 4.0.4 are not applicable.

shallbed[eterminedtobewithinitslimitatthefollowin(g+T)andFf 4.2.3.2 F shallbecalculatedbytheexpressionFf=F 1 10tervals:

a.

Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading, b.

At least once per 31 days of accumulated operation in MODE 1, and c.

Within four hours if the AZIMUTHAL POWER TILT (T ) is > 0.030.

q See Special Test Exception 3.10.2.

+

Excluding the center CEA during Cycle 10.

CALVERT CLIFFS - UNIT 1 3/4 2-9 Amendment No. JJ/JJ/JS//E/7J/

88. 151

l E

'I SURVEILLANCE RE0VIREMENTS (Continued) 4.2.3.3 F shall be determined each time a calculation of Ff is required r

by using the incore detectors to obtain a power distribution map with all full length'CEAs+ at or above the Long Term Steady State insertion Limit for the existing Reactor Coolant Pump combination.

4'.2.3.4 T shall be determined each time a calculation of Ff is required q

and the value of T used to determine Ff shall be the measured value of q

T.

q t

Excluding the center CEA during Cycle 10.

+

1 I'

CALVERT CLIFFS - UNIT 1 3/4 2-10 Amendment No. EUA2,151

u 3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN LIMITING COno-TION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specific &tior, 3.1.1.1 may be suspended for m?rst,ement of CEA-worth-and shutdown mat gin provided reactivity equiv b t to at least the highest estimated CEA worth is available For t:..- :nsertion from OPERABLE CEA(s).

APPllCABILIU: 000E 2.

ACTION:

With any full length CEA+ not rully inserted and with less than l

a.

. the above. reactivity equivalent available for trip insertion, immediately initiate and carotinue boration at 2 40 gpm of 2300 ppm boric acid. solution or its equivalent until the SHUTDOWN MARGIN required by Specification-3.1.1.1-is restored, b.

With all full length CEAs+ inserted and the reactor subcritical by less than the above reactivity equivalent,_ immediately initiate and continue boration at 2-40 gpm of 2300 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE RE0VIRt RIS

~

4.10.1.1 - The position of each full length CEA+ required either partially or fully withdrawn shall bc determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each CEA+Lnot fully inserted shall be oemonstrated capable of l

full insertion when tripped from at least th.' 50% withdrawn position within 7 days prior to reducing the SHU'DOWk '.19CIN to less than the limits of-Specification 3.1.1.1.

Excluding.the'certer CEA during Cycle 10.

9 f,

l CALVERT CLIFFS - UNIT 1 3/4 10-1 Amendment No. 7///E/Jdf, 151

- -

ML20066J166

Text

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