Text

Amend 170 to License DPR-53,revising Facility TS to Support Cycle 11 Operation
	ML20097A928
Person / Time
Site:	Calvert Cliffs
Issue date:	05/26/1992
From:	Capra R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20097A929	List: ML20097A928; ML20097A940;
References
	NUDOCS 9206030272
	Download: ML20097A928 (38)
	v • d • e

_

A Of 0g*

k o

UNITED STATES

~,,

E NUCLEAR REGULATORY COMMISSION n

i I

uAssiNa ton, D. c. rosas

/

BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.170 License No. DPR-53

-1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated December 10, 1991, and supplemented on April 17, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (thu 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 ruses 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.

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. OPR-53 is hereby amended to read as follows:

9206030272 920526 PDR ADOCK-05000317

-P PDR_

_. _,... _ _ _ _ _. _ _ _. ~.

, (2).T.gdw1qpj_Specificati.gni The Technical Specifications cont'ined in Appendices A and B, as revised tnruugh Amendment No. 170, 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 issuaice to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION N U @. [ p./

Robert A. Capra, Director Project 'lirectorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

oby 26,1992 l

1

~

s ATTACHMENT TO LICENSE /tMENDMENTS AMENDMENT NO.170 FAClllTY QPERATING LICENSE NO. OPR-51 DOCKET NO. 50-111 Revise Appendix A as follows:

Remove Paaes Insert Paaes 2-11 2-11 3/4 1-1 thru l-4 3/4 1 I thru l-4 3/4 1-24 thru l-35 3/4 l~24 ttru l-35 3/4-2-1 3/4 ;!-l 3/4 2-3 3/4 2-3 3/4 2-5 thru 2-7 3/4 2-5 thru 2-7 3/4 2-9 thru 2-13 3/4 2-9 thru 2-13 3/4 2-16 3/4 2-16 3/4 2-17 3/4 2-17 3/4 10-1 3/4 10-1 3 3/4 1-4 8 3/4 1-4 8 3/4 1-5 E 3/4 1-5 8 3/4 7-3 8 3/4 7-3 5-4 5-4

- 2.0 - SAFETY LIMITS AND-LIMITIM SAFETY SYSTEM SETTINGS I'#

1 I

i-1 I

l-1

-1.20 (o,0,1,17)

UNACCEPTABLE UNACCEPTABLE-OPERATION OPERATION 1.10 REGION REGION 1.00

(-0.18,1.00 (0.2,1.00)

N i

ik 0.90

~

2

/

0.'80

__ ACCEPTABLE 5:

OPERATIrM 0.70 REGION 0.60 g

~Og o

{ - 0.50 0.40

(-0.6,C.40)

(0.6,0.40) 0.30 0.20 0.15 I

I I

-0.8

-0.6 _ _

- -0.4 _

-0.2 _-

0.0 0.2 -

0.4 0.6 0.8 --

PERIPHERAL AIIAL SHAPE INDEI,Yg FIGURE 2.2-1 l

PERIPflERAL AXIAL SHAPE INDEX, Yr VS. FRACTION OF RATED 'llERMAL POWER

'CALVERT CLIFFS - UNIT 1 2-11

%iendment No. 170 i'

4 a

a,....

s

-,.. - - ~ -=

a..

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T,,, > 200 F LIMITING C0NDITION FOR OP'3ATION 3.1.1.1 The SHUTD0WN MARGIN shall be equal to or greater than the limit line of Figure 3.1.1-1.

APPLICABILITY:

MODES 1, 2", 3, and 4.

ACTION:- With the SHUTDOWN MARGIN less thaa the limit line of Figure 3.1.1-1*, imediately initiate and continue boration at > 40 gpm of 2300 ppm boric acid solution or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be detenniped to be equal to or greater than the limit line of Figure 3.1.1-1*:

a.

Within one hour after detection of an inoperable CEA(s) and at 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 MARGIN shall be increased by an amount at least equal to the withdrawn worth of the imovable or untrippable CEA(s).

l 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.

Adherence to Technical S9ecification 3.1.3.6 as specified in Surveillance Requirement 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.

Wi th K.n > 1.0.

l CALVERT CLIFFS - UNIT 1 3/4 1-1 Amendment No. 170 f

4 l

l 3/4.1 REACTIVITY CONTROL SYSTEMS l

l SURVEII. LANCE REQUIREMENTS (Continued) 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 oy verifying that the predicted critical CEA position j

is withir. the limits of Soecification 3.1.3.6.

d.

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

Specification 3.1.3.6.

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 tnron concentration, 2.

CEA position, 3.

Reactor Coolant System average f emperature, 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 agreament within i 1.0% Ak/k at least once per 31 Effective Full Power Days (EFPD).

This comparison shall consider at least those factors stated in Specification 4.1.1.1.1.e. above. The predicted reactivity values shall be adjusted (normalized) 'o correspond to the actual core c.onditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading, v

I D

I Wi th K,,, < 1.0.

CALVERT CLIFFS - UNIT 1 3/4 1-2 Amendment No. 170 s

3/4.1 REACTIVITY CONTROL SYSTEMS Ih U

Vs

!3

%2 h

i E

2 2

3 4

o 5z E

B*

B B

3 5

i z

e e

a 2

o 8

E g

<O

<5 5

n Ne 8

i i

i

~

(dvs)moavn noamns FIGURE 3.1.1-1 CALVERT CLIFFS - UNIT 1 3/4 1-3 Amendment No. 170 v

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CC'iTROL SHUTDOWN MARGIN - T,,, s 200 F LIMITING CGNDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be 13.0% Ak/k.

APPLICABILITY: MODE 5.

a.

Pressurizer level 190 inches from bottom of the pressurizer, b.

Pressurizer level < 90 inches from bottom of the pressurizer and all sources of non-borated water $ C8 gpm.

ACTION:

a.

With the SHUTDOWN MARGIN < 3.0% Ak/k, imediately initiate and continue boration at t 40 gpm of 2300 ppm boric acid solution or equivalent until the required SHUTDOWN MARGIN is restored.

b.

With the pressurizer drained to 5 90 inches and all sources of non-borated water > 88 gpm, imediately suspend all operations involving positive react vity changes while the SHUTDOWN MARGIM is increased to compensate for the additional sources of non-borated water or redece the sources of non-borated water to 5 88 gpm.

SURFILLANCE REQUIREMENTS 4.1.1.2.1 The SHUTDOWN MARGIN shall be datemined to be 13.0% Ak/k:

a.

Within one hour after detection of an inoperable CEA(s) and at 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 imovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the imovable 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 roncentration, 2.

CEA position, CALVERT CLIFFS - UNIT 1 3/4 1-4 Amendment No. 170

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Full length CEA Position LIMITING CONDITION FOR OPERATION 3.1.3.1 The CEA Motion Inhibit and all shutdown and regulating CEAs shall l

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:

a.

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

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 , 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 2.

Place and maintain the CEA drive system mode switch in 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 l

to less than 5% insertion, or 3.

Se in at least HOT STANDBY.

c.

With one CEA inoperable due to causes other than addressed by l

ACTION a, above, and inserted beyond the Long Tem Steady State 1

Insertion Limits but within its above specified alignment L

requirements, operation in MODES 1 and 2 may continue for up to 7 days per occurrence with a total accumelated time of 514 days per calendar year.

d.

With one CEA incperable due to causes other than addressed by l

ACTION a, above, but within its above specified alignment requirements and either fully withdrawn or within the Long Term Steady Ste.te Ins'.rtion Limits if in CEA group 5, operation in MODES 1 anc 2 may continue.

l See Special Test Exceptions 3.10.2 and 3.10.4.

CALVERT CLIFFS - UNIT 1 3/4 1-24 Amendment No. 170 l

m.

3/4.1 REACTIVITY CONTROL SYSTEMS 1

LIMITING CONDITION FOR OPERATION (Continued)

With one or more CEAs misaligned from any other CFAs in its group l

e.

+

by more than 7.5 inches but less than 15 inches, oparation in MODES 1 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 inoperabic. 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 5 14 days per calendar year provided all of the following conditions are met:

a) The THERMAL POWER level shall be reduced to 5 70% of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump ccmbination within one hour; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used.

b) Within one hour after reducing the THERMAL POWER as required by (a) above, the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 7.5 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1.3-2;-the THERMAL POWER level shall 53 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 MODES 1 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 tima allowance detennined by the Better Axial Shape Selection System (BASSS) or, if the BASSS time allowance is unavailable, the time-allowance shown in Figure 3.1.3-1.

If Figure 3.1.3-1 is used, the precisaligned Pi value used to detennine the allowable time to reaiign the CEA from Figure 3.1.3-1 shall be the latest-measurement taken within 5 days prior to the CEA misalignment.

If no measurements were taken within 5 days prior to the misalignment, a pre-misaligned P, of 1.70 shall be assumed.

l l

CALVERT CLIFFS - UNIT 1 3/4 1-25 Amendment No. 170 d

r m

,.-n

,w.

3/4.1 REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) 9 With one CEA misaligned from any other CEA in its group by 15 inches or more at the conclusion of the 3ennitted time allowance, imediately start to implement tie following actions:

1.

If the THERMAL POWER level prior to the misaligranent was greater than 50% of RATED THERMAL P0WER THERMAL POWER shall be reouced to less than the greater of:

a) 50% of RATED THERMAL F0WER b) 75% of the THERMAL POWER level prior to the misalignment within one hour after exceeding the permitted time allowance.

l 2.

If the THERMAL POWER level prior to the misalignment was 5 50% of RATED THERMAL POWER, maintain THERMAL POWER no higher than the value prior to the misaligr. ment.

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 l

inoperable POWER OPERATION may continue fcr up to 7 days per l

occurrence with a total accumulated time of 5 14 days per calendar year provided the remainder of the CEAs 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 3.1.3-2; the l

THERMAL POWER 1evel shall be restricted pursuant to l'

Specification 3.1.3.6 during subsequent operation.

i h.

With more than one CEA inoperable or misaligned from any other l

CEA in its group by 15 inches (indicated position) or inore, be in l

at least NOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , l

l I

CALVERT CLIFFS - UNIT 1 3/4 1-26 Amendment No. 170 f

. ~..

3/4.1 REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

i. - For the purposes of performing the CEA operability test of l

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 network) cannot be restored within ten minutes from the cannencement 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 connencement of CEA motion.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each CEA shall be determined to be within l

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 .

4.1.3.1.2 Each CEA not fully inserted shall be determined to be OPERABLE l

by 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 OPERA 4LE at least once per 31 days by a functional test which verifies that the circuit-maintains the CEA group overlap and sequencing requirements of Specification 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

~(indicatedposition).

I 4

i CALVERT CLIFFS - UNIT 1 3/4 1-27 Amendment No. 170 c

3/4.1 REACTIVITY CONTROL SYSTDt3 E

~

m 8

t 1

0 nu e

G w

3

-l 3

2N 3

~

l

~

l

/

q 5

3 h

h 2

i g.

3 i

l g

~

l iiiiiiiriliiiite,,,l.,,,,,,,,l,,,,,,,,,l,,,,,,,,,j,,,,,,,,,j,,,,,,,,, _q-iiiiiiiii

~

a 8

8 S

S 3

g g

Lmt1NmovsaNormru atunu.

FIGURE 3.1.3-1

-ALLOWABLE TIME-TO REALIGN CEA YERSUS INITIAL TOTAL INTEGRATED RADIAL PEAKING FACTOR CALVERT CLIFFS - UNIT 1-3/4 1-28 Amendment-No. 170

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Position Indicator Channels LIMITING CONDITION FOR OPERATION 3.1.3.3 At least two of the following three CEA position indicator channels shall De OPERABLE for each shutdown and regulating CEA:

l a.

CEA voltage divider reed switch position indicator channel, capable of determining the absole:e CEA position within i 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 cf the applicable position indicator; and c.

CEA pulse counting position indicator channel.

APPLICABILITY: MODES 1 and 2.

ACTION:

a.

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

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 OPEP.ABLE status, or b

b)

Be in at least HOT STANDBY, or c)

Reduce THERMAL POWER to < 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 l

indicator is fully withdrawn while maintaining l

CALVERT CLIFFS - UNIT 1 3/4 1-29 Amendment No. 170

1 3/4.1 REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) the withdrawal sequence required by Specification 3.1.3.6 and when this CEA group reaches its fully withdrawn positior 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 wfthdrawing 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 i

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 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, or, 2.

If the failure existed before entry into M0DE 2 or occurs prior to an "all CEAs out" configuration, the CEA grou; ts) l with inoperable 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 3.3.3.3 above.

b.

With more than one CEA per group having its CEA pulse c~.ing l

position indicator channel and either (1) the " Full Out" o. " Full In" position indicator, or (2) the voltage divider position 1

indicator channel inoperable, operation in MODES 1 and 6

l CALVERT CLIFFS - UNIT 1 3/4 1-30 Amendment No. 170

3/4.1 REACTIVITY CONTROL SYSTEMS i.IMITING CONDITION FOR OPERATION (Continued) 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 er fully inserted as verified by actuation of the applicable position indicator.

SURVERLANCE REQUIREMENTS 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 l

-channels agree within 4.5 inches, or

-c.

Verifying 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 channels shall be l

made at leest once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l l

CALVERT CLIFFS - UNIT 1 3/4 1-31 Amendment No. 170

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES CEA Drop Time LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) CEA drop time, l

from a fully withdrawn position, shall be 5 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:

a.

T,,, > 515*F, and b.

All reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTION:

a.

With the drop time of any full length CEA determined to exceed I

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 detennined at less 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 drap time determination.

SURVEILLANCE REQUIREMENTS

~

4.1.3.4 The CEA drop time of full length CEAs sh :1 be demonstrated l

through measurement prior to reactor criticality:

a.

For all CEAs following each removal of the reactor vessel head, b.

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

At least once per REFUELING INTERVAL.

I CALVERT CLIFFS - UNIT 1 3/4 1-32 Amendment No. 170

-.3/4.1 REACTIVITY CONTR02 SYSTEMS -

3/4.1.3 MOVABLE CONTROL ASSEMBLIES Shutdown CEA Insertic3 Limit LIMITING CONu1 TION FOR OPERATION 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 either:

a.

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

Declare the CEA inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown CEA shall be detemined to be withdrawn to at least 129.0 inches:

a.

Within 15 minutes prior to withdrawal of any CEAs in regulating l

groups during an approach to reactor criticality, and b.

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

l L

l See Special Test Exception 3.10.2.

Wi th K.,, > 1.0.

l CALVERT CLIFFS - UNIT 1 3/4 1-33 Amendment No. 170 l

3/4.1 REACTIVITY CONTROL SYSTEMS-3/4.1.3 MOVABLE CONTROL ASSEMBLIES Reaulatina CEA Insertion Limits _

LIMITING CONDITION FOR OPERATION 3.1.3.6 The regulating CEA groups shall be limited to the withdrawal l

sequence and to the insertion limits shown on Figure 3.1.3-2 (regulacing CEAs are considered to be fully withdrawn in accordance with Figure 3.1.3-2 when withdrawn to at last 129.0 inches) with CEA insertion between the Long Tem Steady State.nsertion Limits and tne Transient Insertion Limits restricted to:

a.

5 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.

5 5 Effective Full Power Days per 30 Effective Full Power Day interval, and c.- 514 Effective Full Power Days per calendar year, i.

APPLICABILITY: MODES 1* and 2*'.

ACTION:

a.

With the regulating CEA groups inserted beyond the Transient l

Insertion Limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, within two hours either:

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 POWE" which is allowed by the CEA group position using Figure '.1.3-2.

b.

With the regulating CEA groups inserted oetween the Long Tem l

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 3.1.3-2 are not exceeded, or I

See Special Test Exceptions 3.10.2 and 3.10.4.

With K,, > 1.0.

CALVERT CLIFFS - UNIT 1 3/4 1-34 Amendment No. 170

3/4.1 REACTIVITY CONTROL SYSTEMS LINITING CONDITION FOR OPER/. TION (Continued) 2.

Any subsequent increase in THERMAL POWER is restricted to

< 5% of RATED THERMAL POWER per hour, c..

With the regulating CEA groups inserted between the Lo;:g Tem l

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

1.

Restore the regulating groups to within the Long Tenn Steady i

State Insertion Limits within two hours, or s

2.

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

SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each regulating CEA group shall be detemined to l

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 Alann 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 .

l CALVERT CLIFFS - UNIT 1 3/4 1-35 Amendment No. 170

3/4.2 POWER DISTRIBl! TION LIMITS 3/4.2.1 LINEAR HEAT RATE LIMITING CONDITION FOR OPERATION 3.2.1 The linear heat rate shall not exceed the limits shown on Figure 3.2.1-1.

APPLICABILITY: MODE 1.

ACTION: With the linear hea*. rate exceeding its limits, as indicated by four or more coincident incore channels or by the AXIAL SHAPE INDEX outside

(

of the power dependent control limits of Figure 3.2.1-2, within 15 minutes initiate corrective action to reduce the linear heat rate to within the sl limits and either:

a.

Restore the linear heat rate to within its limits within one g

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 .

SURVEILLANCE REQUIREMENTS 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 by continuously monitoring the core power distribution with either the Excore Detector Monitoring System or with the Incore Detector Monitoring Svstem.

4.2.1.3 Excore Detector Monitoring 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 1

are withdrawn to and maintained a6 or beyond the Long Tenn Steady State Insertion Limit of Specification 3.1.3.G.

b.

Verifying at least once per 31 days that the AXIAL SHAPE INDEX alann setpoints are adjusted to within the limits shown on Figure 3.2.1-2.

CALVERT CLIFFS - UNIT 1 3/4 2-1 Amendment No. 170

3/4.2 POWER DISTRIBUTION LIMITS 8

a:

Z O

Z E

O i

i s

e s

l.

5

.)

8 3

s 8

l 8=

S S

S (HOLYH2GON + GYIO + TdAO LI/MM 'ELVH J,V8H HVENTI 3YEd TIEYMOT1Y FIGURE 3.2.1-1 ALLOWABLE PEAK LINEAR HEAT RATE VS. TIME IN CYCLE CALVF.RT CLIFFS - UNIT 1 3/4 2-3 Amendment No. 170

I:

3/4.2 POWER DISTRIBUTION LIMITS k

o.

8 6

- b

- 3 k

- 4

a C

M

- 3 6<

~~ b q

a

~~$

l l

1 g

3 E

E a"

z FIGURE 3.2.1-3 TOTAL PLANAR RADIAL PEAKING FACTOR VS. N CALVERT CLIFFS - UNIT 1 3/4 2-5 Amendment No. 170

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - FTy LIMITING CONDITION FOR OPERATION 3.2.2.1 The calculated value of P,, shall be limited to 51.70.

l APPLICABILITY: MODE 1*.

ACTION: With P,, > 1.70, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a.

Withdraw and maintain the full-length CEAs at or beyond the Long Tem Steady State Insertion Limits of Specification 3.1.3.6 and reduce THERMAL POWER as follows:

1.

Reduce THERMAL POWER to bring the combination of THERMAL POWER and FI,within the limits of Figure 3.2.2-1, or 2.

Re uce THERMAL POWER to less than or equal to the limit established by the Better Axial Shape Selection System (BASSS) as a function of P,,; or b.

Be-in at least NOT STfJD8Y.

SURVEILLANCE REQUIREMENTS 4.2.2.1.1.The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 P,, shall-be calculated as P = F,d to be within its limit at the using a full core power y

distribution system.

P,, shall be detemine following intervals:

a.

Prior to operrtion above 70 percent of RATED THERMAL POWER after

-each fuel loading, b.

At :least once per 31 days of accumulated operation in M00E 1, and j-c.

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

l See Special Test Exception 3.10.2.

CALVERT CLIFFS - UNIT 1 3/4 2-6 Amendment No. 170

3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.1.3 P shall be determined each time a calculation is required by l

y using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Tem Steady State Insertion Limit for the l

existing Reactor Coolant Pump combination.

This detemination shall be

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

CALVERT CLIFFS - UNIT 1 3/4 2-7 Amendment No. 170 1

2

3/4.2 _ POWER DISTRIBUTION LINITS 3/4.2.2 TOTAL PLANAR RADI AL PEAKING FACTOR - F!,

L7MITING CONDITION FOR OPERATION 3.2.2.2 The value of N presently used in Specification 4.2.1.3 shall be in accordance with Figure-3.2.1-3.

APPLICABILITY: M0DE 1 when operating in accordance with Specification 4.2.1.3.

ACTION: With the value of N presently used in Specification 4.2.1.3 exceeding-the limit shown in Figure 3.2.1-3, 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 3.2.1-3; or

- b.

Be in at least NOT STANOBY.

SURVEILLANCE REQUIREMENTS 4.2.2.2.1 -The provisions of Specification 4.0.4 are not applicable, r 4.2.2.2.2 P shall be calculated as P = F using a full core power y

distribution mapping system. N shall IIe deTemined to be within its limit by monitoring P at the following intervals:

y a.

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

b.

At least once per 3 days of accumulated operation in ME 1.

CALVERT CLIFFS - UNIT 1 3/4 2-9 Amendment No. 170

-3/4.2. POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.2.3. FI shall be determined each time a calculation is required by l

using the inc, ore detectors to obtain a power distribution map with all full length CEAs at or above the Long Tem Steady State. Insertion Limit for the l

existing Reactor Coolant Pump combination.

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

i.

CALVERT CLIFFS - UNIT 1 3/4 2-10 Amendment No. 170

.~

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.3-TOTALINTEGRATEDRADIALPEAKINGFACTOR-FJ LIMITING CONDITION FOR OPERATION 3.2.3 The-calculated value of P, shall be limited to 51.70.

I APPLICABILITY: MODE 1*.

ACTION: - With P,? 1.70, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

l a.

Be in at least NOT STANDBY, or b.. Withdraw and maintain the full length CEAs at or beyond the Long Tem Steady State Insertion Limits of Specification 3.1.3.6 and reduce THERMAL POWER as follows:

1.

Reduce THERMAL-POWER to bring the combination of THERMAL POWER and F, within the limits of Figure 3.2.3-1, or 2.

Reduce THERMAL POWER to less than or equal to the limit established by the Better Axial C'. ape Selection System (BASSS) as a function of P,.

When the THERMAL POWER is detemined from Figure 3.2.3-1, it shall be used to establish a revised -@per THERMAL POWER LEVEL limit on Figure 3,. 3-2 -(i.e., Figure 3.2.3-2 shall be truncated at the allowable fraction of RATED THERMAL POWER detemined by Figure 3.2.3 1). Subsequent operation shall-be maintained within the. reduced acceptable operation region of Figure 3.2.3-2.

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

P, shall be calculated as P = F,detemined to be within its limit 4.2.3.2 using a full core power distribution _ mapping-system.: F, shall be 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 accumulated operation in M00E 1, and c.

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

See Special Test Exception 3.10.2.

CALVERT CLIFFS - UNIT 1 3/4 2-11 knendment No. 170

e a.

3/4.2-PWER DISTRIBUTION LIMITS E'JP,YETLLANCE REQUIREMENTS (Continued) 4.2.3.3 P, shall be detennined each time a calculation is required by l

using the incore detectors to obtain a power distribution map with all full

_ length CEAs at or ?i.)ve the Long Term Steady State Insertion Limit for the 1

existing Reactor Coolant Pump combination.

a l

l l

l-l CALVERT-CLIFFS - UNIT 1 3/4 2-12 Amendment No. L/0

. ~.

3/4.2 POWER DISTRIBUTION LIMITS f

_4 E

e i

/

c 5

r l5 o

"U if 2

5 3"5

~

H e

l l

1 3

3 3

5 3

2 Exmod Trmunu a2LYH do NOLwVHd YmVMUTIY FIGURE 3.2.3-1 TOTAL INTEGRATED RADIAL PEAXING FACTOR VS.

ALLOWABLE FRACTION OF RATED THERKAL POWER CALVERT CLIFFS - UNIT 1 3/4 2-13 Amendment No. 170

.e

3/4.2 P0 HEW DISTRIBUTION LIMITS 3/4.2.5 MB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintainec within the limits shown on Table 3.2-1:

a.

Cold Leg Temperature b.

Pressurtzer Pressure c.

Reactor Coolant System Total Flow Rate d.

AXIAL SHAPE INDEX, THERMAL POWER.

l APPLICABILITY: H0DE 1.

ACTION; With any of the above parameters exceeding its limit, restore the parameter to 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 thar 5% of RATED THERMAL POWER w1 thin the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEIll).NCE REQUIREMENTS 4.2.5.1 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.2.5.2 The Reactor Coolant System total flow rate shall be determined to be within its limit by measurement at least once per 18 nonths.

4.2.5.3 The Better Axial Shape Selection System (BASSS) may be used for mor.itoring THERMAL POWER as a function of AXIAL SHAPE INDEX.

BASSS monitoring shall be limited to CEA insertions of the lead bank s 55%.

CALVERT CLIFFS - UNIT 1 3/4 2-16 Amendment No. 170

l I

I g,

TABLE 3.2-1 R

G t

INIS PARAMETERS N

i l

[

C LIMITS 7

in

=

FOUR REACTOR TNREE REACTOR TWO REACTOR TWO REACTOR G

c C00LAllT PUMPS COOLANT PUMPS C00UWT PUMP 3 COOLANT PUMPS Y

}

PARAMETER OPERATIM OPERATIN OPERATI E-SAME LOOP OPERATIM-SPPOSITE LOOP r

b Cold Leg Temperature

< 548 F 5

r-1 Pressurizer Pressure 1 2200 psia.

g i

Reactor Coolant System Total Flow-1 370,000 gpm

[

Rate j

y AXIAL SNAPE IleEX,.

t THERMAL POWER l

I i

L Limit not applicable during either a 4NERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a TMEMAL POWER step increase of greater than 10% of RATED THERMAL POWER.

k **

These values left blank pending NRC approval'of ECCS analyses for operation with less than four

[

R reactor coolant pumps operating.

l 5

The AXIAL SNAPE IISEX, THEMAL POWER shall be maintained within the limits established by the l

l

e Better Axial Shape Selection System (BASSS) for.CEA insertio7s of the lead bank of < 55% when l

BASSS.is SPERABLE, or within the limits of Figure 3.2.3-2 for CEA insertions specified by g

Figure 3.1.3-2.

i i

l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 M'fTDOWN MARGIN LIMITING CONDITION FOR OPERATICN 3.10.1 The SHUTDOWN MRGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and SHUTDOWN MRGIN provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s).

ApPLICA3IllTY: MODE 2.

ACTION:

a.

With any full length CEA not fully inserted art with less than l

the above reactivity equivalent available for i. rip insert'>n, immediately initiate and continue boration at t 40 gpm of 2300 ppm boile acid solution or its equivalent until the SHUTDOWN MRGIN required by Speciff',ation 3.1.1.1 is restored, b.

With all full length CEAs inserted and the reactor subcritical by l

1ess than the above reactivity equivalent, imediately initiate and continue boration at t 40 gpm of 2300 ppm boric acid solution or its equivalent until the SHUTDOWN MRGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length CEA required either partially or l

fully withdrawn shall be detennined 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 not fully inserted shall be demonstrated capable of full l

insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MRGIN to less than the limits of Specification 3.1.1.1.

h l

CALVERT CLIFFS - UNIT 1 3/4 10-1 Amendment No. 170

I

}

I 3/4.1 BEACTIVITY M TROL SYSTEMS BASE $

j The ACTION statements applicable to a stuck or untrippable CEA and to a large n.isalignment (t 15 inches) of two or more CEAs, require a prompt

{

shutdown of the reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event tJ,s st;,d or untrippable CEA, the loss of SHUTDOW MARGIN.

For small misalignments (< 15 inches) of the CEAs, there is 1) a small degradation in the peaking factors relative to those assumed in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 2) a small effect on the time dependent long tenn power distributions relative to those used in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 3) a small effect on the available SitUTDOWN MARGIN, and 4) a small effect on the ejected CEA worth used in the safety analysis.

Therefore, the ACTION statement associated with the small misalignment of a CEA permits a one hour time interval during which attempts may be made to restore the CEA to within its alignment requirements prior to initiating a reduction in THERMAL POWER.

The one hour time limit is sufficient to (1) identify causes of a misaligned CEA, (2) take appropriate corrective action to realign the CEAs and (3) minimize the effects of xenon redistribution.

Overpower margin is provided to protect the core in the event of a large misalignment (2 15 inches) ef a CEA.

!10 wever, this misalignment would cause distortion of the core power distribution.

The Reactor Protective System would not detect the degradation in radial peaking factors and since variations in other system parameters (e.g., pressure and coolant temperature) may not be sufficient to cause trips, it is possible that the reactor could be operating with process variables less conservative than those assumed in generating LCO and LSSS setpoints. The ACTION statement associated with a large CEA misalignment requires prompt action to realign the CEA to avoid excessive tra.rgin degradation.

If the CEA is not realigned within the given time construints, ACTION is soecified which will preserve margin, including reductions in THERMAL POWER.

For a single CEA misalignment, the tima allowance to realign the CEA (Figure 3.1.3-1 or as determired by BASSS) is permitted for the following I

reasons:

1.

The margin calculations which support the power distribution 8.COs for DNBR ara based on a steady-state P, as specified in Technical Specification 3.2.3.

2.

When the actual P, is less than the Technical Specification value,--additional margin exists.

i l

CALVERT CLIFFS - UNIT 1 B 3/4 1-4 Amendment No. 170

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3.

This additional margin can be t.redited to offset the increase in P, with time that will occur following a CEA misalignment due to xenon redistribution.

The requirement to reduce power level after the time limit of Figure 3.1.3-1 or after the time limit det mined by BASSS is reached l

offsets the continuing increase in P, that can occur due to xenon redistribution. A power reduction is not required below 50% power.

Below 50% power there is sufficient conservatism in the DNB power distribution LCOs to completely offset any, or any additional, xenon redistribution effects.

The ACTION statements applicable to misaligned or inoperable CEAs include requirements to align the OPERABLE CCAs in a given group with the inoperable CEA. Confomance with these alignment requirements brings the core, within a short period of time, to a configuration consistent with that assumed in generating LCO and LSSS setpoints.

However, extended operation with CEAs significantly inserted in the core may le&d to perturbations in 1) local burnup, 2) peaking factors, and 3) available SNUTDOWN MARGIN wh.ch are more adverse than the conditions assened to exist in the safety analyses and LCO and LSSS setpoints detemination.

Therefore, time limits have been imposed on operation with inoperable CEAs to preclude suct' adverse conditions from developing.

OPERABILITY of the CEA position indicators is required to detemine CEA positions and thereby ensure compliance with the CEA alignment and insertion limits and enst.res proper operation of the rod block circuit.

The CEA ' Full In" and " Full Out' limits provide an additional independent means for detarmining the CEA positions when the ':EAs are at either their fully inserted or fully withdrawn positions.

Therefore, the OPERABILITY and the ACTION statements applicable to inoperable CEA position indicators pemit continued operations when positions of CEAs with inoperable indicators can be verified by the " Full In" or " Full Out" limits.

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

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

The surveillance requirements affecting CEAs with inoperable position indication channels allow 10 minutes for testing each affected CEA. This time limit was selected so that 1) the time would be long enough for the required testing, and 2) if all position indication were lost during testing, the time would be short enough to allow a power reduction to 70%

of maximum allowable THERMAL POWER within one hour from when the testing CALVERT CLIFFS - UNIT 1 B 3/4 1-5 Amendment No. 170

,ip

--m c-g-

y#e-

-g--+-

-yq

---y p.

vt rTN

3/4./ PLANT fYSTEMS BASES In the spectrum of events at 41yzed in which automatic initiation of auxiliary feedwater occurs, the following flow conditions are allowed with an operator action time of 10 minutes.

(1)-

Loss of Feedwater 0 gpm Auxiliary Feedwater Flow (2)

Feedline Break 0 gpm Auxiliary feedwater Flow (3)

Main Steam Line Break 1550 gpm Auxiliary Feedwater l

Flow (This beirf the maximum flow through the AFW suction line, with one unit requiring flow, prior to ump cavitation due to low NPSH.

At 10 minutes after an Auxiliary Feeowater Actuation Signal the operator is assumed to be available to increase or decrease auxiliary feedwater flow to that required by the Fxisting plant conditions.

3/4.7.1.3 Condensate Storace Tank The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at NOT ITANOBY conditions for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with steam discharge to atmosphere with concurrent and total loss of offsite power.

The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

3/4.7.1.4 Activity The limitations on Secondary System specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of l

10 CFR Part 100 limits in the event of a steam line rupture.

This dose also includes the effects of a coincident 1.0 GPH pr -ary to secondary tube d

leak in the steam generator of the affected steam 1..s and concurrent loss of offsite electrical power.

These values are consistent with the assumptions used in the accident analyses.

3/4.7.1.5 Main Steam Line Isolation Valves The PPERABILITY of the main staam line isolation valves ensuras that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the l

event the steam line rupture occurs within containment.

'he OPERABILITY of l

CALVERT CLIFFS

-UNIT 1 B 3/4 7-3 Amendment No. 170

o l

5.0 DE5!GN FEATURLS 4

l DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 50 psig and a temperature of 276'F.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall s antain 217 fuel assemblies with each fuel assembly containing a maximum of 176 fuel rods clad with Zirealoy-4.

Each fuel rod shall have a nominal -active fuel length of 136.7 inches and contain a maximum total weight of 3000 grams uranium.

The initial core

- loading shall have a maximum enrichment of 2.99 weight percent U-235.

deload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.35 weight percent U-235.

l 5.3.2 Except for special test as authorized by the NRC, all fuel assemblies under control element assemblies shall be sleeved with a sleeve design previously approved by the NRC.

r0NTROL ELEMENT ASSEMBLIES 5.3.3 The reactor core-shall contain 77 full length and no part length control element assemblies.

5,4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant of the applicable Surveillance Requirements, b.

For a pressure of 2500 psia, and c.

For a temperature.of 650 F, except for the pressurizer which is 700 F.

CALVERT CLITFS -

f -1 5-4 Amendment No. 170 i

.-_.._m.-,_

.-..._.,..-m.m.

,,. _ _, - _ -.,

ML20097A928

Text

Attachment:

Navigation menu

Search