ML20104A282

Proposed Tech Specs to Improve Reliability of RCS PORVs & Associated Block Valves for Overpressure Protection During Normal Operation & Anticipated Transients

ML20104A282
Person / Time
Site:	Calvert Cliffs
Issue date:	09/01/1992
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20104A269	List: ML20104A264 ML20104A282
References
NUDOCS 9209110127
Download: ML20104A282 (24)

Text

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i ATAM 31ENT 1 UNIT 1 ItEVISED TECilNICAL SPEClflCATION AND llASES PAGES CliANGE NO.1 3/447 113/442 CilANGE NO. 2 3/4432 3/4433 3/4434 113/4 4-10 NOTE: In the INSEltTs, wording which is a change from the current Technical Specifications is underlined.

fjR09110127 92o901 p

ADOCK 05000317 PDR

3/4.4 NEACTOR C0OLANT SYSTEM 3/4.4.3 RELIEF YALVES LIMITING CONDITION FOR OPERATION 3.4.3 Two power-operated relief valves (PORVs) and their associated block valves shall be OPER8.BLE.

AFPLICABILITY: N0 DES 1, 2, and

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a With-one-or-mere-PORV{s)-4noperable; within-1-hour-either-restore the-PORV { s)-to-OPERABLE-s t at tts-eM4 ose-the-a s soc 4 a ted-bl ock valve (s-)-and_raeve nower from4he41eck-valve (s)t-ethemiser-be in-at-least-NGT-STAND 9Y withirrthe next-6-hours and-in-COLS

$NUTDOWN vithin-the-fellowing-30-hours.

A-With-one-or-ere block-valve {s)-inoperable,-within 1:hmtr~etther restore-the-block valTe(t)-to-OPERA 9LE-statur-or-close-the 51ock valve (s)-erd re.T. eve power fre,T, the41ock-valve (s}t-otherwise,-be 4nat-least-N07-STAND 5Y-within the-next-6-hours-and-irr-t0LD-he-fo14 ewing-3040erss h

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-$URVEILLANCE REQUIREMENTS 4.4.3.1 Each PORV shall be demonstrated CPERABLE:

a.

At least once per 31 days by perfomance of a CHANNEL FUNCTIONAL TEST, in accordance with Table 4.3-1, Item 4.

b.

At least once per 18 months by perfomance of a CNANNEL CALIBRATION.

4,4.3.2 Each block valve shall be demonstrated OPERABLE at least once p r

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s-en-0 Qpower-cemovedf6 meet SpeciNcation 3.4.3 $w. ort b

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.CALVERT CLIFFS - UNIT 1 3/4 4-7 Amendment No. M9/

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INSERT A (for Technical Specification 3.4.3 Actions) a.

]f one or igh POP.V(s) has execssive seat leakan, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> close the associated block valve (s) and maintain power la the block valve (s).

b, With one PORV inoperable due to causes other than excessive PORV seat leakas, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to GPERABLE status or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 5 days or be in llOT STANDDY within the next H hours and at or below 355'F within the following M hours.

c.

With both PORVs inoperable due to causes other than egessive PORV seat leakace. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore one PORV to OPERABLE status or close the associated block valve and remove oower from the block vr've: restore one PORV to OPERABLE status within the followine 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in IIOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and at or below 3l!5

• F within the followine 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

- d.

With one or both block valve (s) inoperabic, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valve (s) to OPERABLE status or place its associated PORV(s) in override closed. Restore at least one block valve to OPERABLE status within the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if both block valves are inoperable: restore any remainine inoncia, hic block valve to OPERABI,E status within the followine 5 davst otherwise, be in at least IlOT STANDBY within the next g hours and at or below 355

• F within the following M hours.

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4 INSERT B (for Technical Spc 'ification 3/4.43)

Above 355 *E At or below 355 'F. Specification 3/4.4.9.3 applies, l

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3/4.4 REACTOR COOLANT SYSTEM BASES shutdown cooling loop, connected to the RCS, provides overpressure relief.

capability and will prevent RCS overpressurization.

During operation, all pressurizer code safety valves must bc OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 psia.

The combined relief capacity of these valves is sufficient to limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss of turbine generator load while operating at RATED THERKAL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power-operated relief valve or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during i

shutdown and will be performed in accordance with the provisions of Section XI of the ASHE Boiler and Pressure Vessel Code.

3/4.4.3 RELIEF VALVES The power-operated relief valves (PORVs below the setting of the pressurizer co)e safety valves. operate to relieve RCS d

These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emergency ogyout e to egur3L.tQb311yJp_3ealth Dq possibie RCS 1eakage path.

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e aclalee LaJk a4 f ak, n+ meed emeqcacy ggnT-6 N4.4.4 PRESSURIZER P

/s A steam bubble in the pressurizer with the level as programed ensures that the RCS is not a hydraulically solid system and is capable of accomodating pressure surges during operation. The operating band for pressurizer level bounds the programed level and ensures that RCS pressure remains within the bounds of an analyzed condition during the excessive charging event as well as during the limiting depressurization event, Excess Load. The operating band also protects the pressurizer code safety valves and power-operated relief valve against water relief. The power-operated relief valves function to relieve RCS pressure during all design transients.

l Operation of the power-operated relief valve in conjunction with a reactor j

trip on a Pressurizer-Pressure-lligh signal, minimizes the undesirable opening of the spring-loaded pressurfzer code safety valves.

)

The requirement that 150 kw of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency CALVERT CLIFFS - UNIT 1 0 3/4 4-2 knendment No. f49

INSERT C (for 11 ASliS 3/4.4.3)

The block valves are exempt from the sutveillance requirements to cycle the valves when they have been closed to comply with the AQJ1QN.JysuirementsJ This precludes the need to cycle the vahn 1

with full system differential pressure or when maintenance is beine performed to restore an inoperable PORV to OPERA 131.E status.

Ihwpr is maintained to the block valve when it is closed to control excessive PORV seat leakacca This allows the PORV and block valve to remain operabh squid the PORV be needed to control reactor pressure and facilitate decay heat removal durinc certain accident conditions. The removal of nower from a closed block valve for a PORV inonerable due to causes other than excessive PORV seat leakace provides additional assurance that the block. lve will not be inadvertently onened when a

the condition of the PORV is uncertain.

RCS temperature, as used in the annlicability statement. is determined as follows- (1) with the RCPs runnine. the RCS cold lec temocrature (Tc) is the apprentiate indication. (2) with the Shutdown Cooline System in operation. the shutdown cooline temperature indication is annropriate. (3) if neither the RCPs or shutdown cooling is in operation. the core exit thermocounles are the appropriate indicators of RCS temperature.

The testine for trancStrinc motive and control oower for the PORVs and block valves from the normal to emercenev nower bus is donc under Technical Snecification 4 A1.1.2.d.3.

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i 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Overpressure Protection Systems I.IMITING CONDITION FOR OPERATION 3.4.9.3 The following overpressure protection requirements shall be met:

a.

One of the following three Overpressure Protection Systems shall be in place:

1.

Two power-operated relief,JalvesjEO,RVsj with_adt

/v s 43 setpoint 5 429 psia (5r 44 4

7 A single PORY with a trip setpoint of 5 429 psiah a 2.

4 i

Reactor Coolant System vent of 11.3 square inches, or assui d e uc lc 3.

A Reactor Coolant System (RCS) vent t 2.6 square inches.

b.

Two high pressure safety injection (HPSI) pumps' shall be disabled by either removing (racking out) their motor circuit breakers from the electrical power supply circuit, or by locking shut their discharge valves.

The HPSI loop motor operated valves (HOVs)' shall be prevented c.

from automatically aligning HPSI pump flow to the RCS by placing their hand switches in pull-to-override.

d.

No more than one OPERABLE high pressure safety injection pump with suction aligned to the Refueling Water Tank may be used to inject flow into the RCS and when used, it must be under manual control and om of the following restrictions shall apply:

1.

The total high pressure safety injection flow shall be limited to 5 200 gpm OR l

2.

A Reactor Coolant System vent of 12.6 square inches shall exist.

e.

When not in use, the above OPERABLE high pressure safety injection pump shall have its handswitch in pull-to-lock.

APPLICABILITY: When the RCS temperature is 5 355*F and the RCS is vented l

to < 8 square inches.

EXCEPT when required for testing.

CALVERT CLIFFS - UNIT 1 3/4 4-32 Amendment No. p.1 j

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3/4.4 REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued) l

_ _ _ _, _ _ _ ~ ~ _ _ _

s put>g3 wyx & ks knnakee asr*f et M NWJ)

ACTION:

a.

With one PORY inoperabl either restore the inoperable PORV to OPERABLE status within 5 days or depressurize and vent the RCS through a > 1.3 square inch vent (s) within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />;

[N

d'N maintain tIie RCS in a vented condition until both PORVs have been restored to OPERABLE status.

, I?MffTD %

With both PORVs inoperable, depressurize and vent the RCS through a 12.6 square inch vent (s) within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />; maintain the RCS in a vented condition until either one OPERABLE PORY and a vent of 11.3 scuare inches has been established or both PORVs have been restorec to OPERABLE status, l

l h In the event either the PORVs or the RCS vent (s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient and any corrective action necessary to prevent recurrence.

h" With less than two HPSI pumps' disabled, place at least two HPSI pump handswitches in pull-to-lock within fifteen minutes and disable two HPSI pumps within the next four hours.

h With one or more HPSI loop HOVs' not prevented from automatically aligning a HPSI pump to the RCS, imediately place the MOV handswitch in pull-to-override, or shut and disable the affected HOV or isolate the affected HPSI header flowpath within four hours, and implement the ACTION requirements of Specifications 3.1.2.1, 3.1.2.3, and 3.5.3, as applicable.

With HPSI flow exceeding 200 gpm while suction is aligned to the l

RWT and an RCS vent of < 2.6 square inches exists, 1.

Imediately take action to reduce flow to less than or equal to 200 gpm.

l 2.

Verify the excessive flow condition did not raise pressure above the maximum allowable pressure for the given RCS temperature on Figure 3.4.91 or Figure 3.4.9-2.

EXCEPT when required for testing, CALVERT CLIFFS - UNIT 1 3/4 4-33 Amendment No.,L7i/

L

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INSERT D (new Technical Specification 3.4.93 Action b) h.

With one PORV inoperable in Modes 5 or 6, either restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or depressurize and vent the RCS through a A 13 square inch vent (s) within the next E hours., and maintain the RCS in this vented condition until both PORVs have been restored to OPERABLE status.

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3/4.4 REACTOR COOLANT SYST_Di LIMITING CONDITION FOR OPERATION (Continued) 3.

If a pressure limit was exceeded, take action in accordance with Specification 3.4.9.1.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.4.9.3.1 Each PORY shall be demonstrated OPERABLE by:

a.

Performance of a CHANNEL FUNCTIONAL TEST on the PORY actuation l

channel, but excluding valve operation, within 31 days prior to i

entering a condition in which the PORY is required OPERABLE and i

at least once per 31 days thereafter when the PORY is required OPERABLE.

b.

Perfomance of a CHANNEL CALIBRATION on the PORY actuation channel at least once 18 months.

c.

Verifying the PORY t

valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the P0 eing used for overpressure protection.

d.

Testing in accordance with the inservice test requirements i

pursuant to Specification 4.0.5.

4.4.9.3.) hen the vent (s) is being used for overpressure protection.The RCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> w 4.4.9.3.3 All high pressure safety injection pumps, except the above OPERABLE pump, shall be demonstrated inonerable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l

by verifying that the motor circuit breakers have been removed from their electrical power supply circuits or by verifying their discharge valves are locked shut.

The automatic opening feature of the high pressure safety injection loop MOVs shall be verified disabled at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The above OPERABLE pump shall be verified to have its handswitch in pull-to-lock at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l Except when the vent pathway is locked, sealed, or otherwise secured in the open position, then verify these vent pathways open at least once per 31 days.

CALVERT CLIFFS - UNIT 1 3/4 4 34 AmendmentNo.17/

1

3/4.4 JLEACTOR C00LMT SYSTEM BASES A pressurizer steam volume and a single PORY will provide satisfactory control of all mass addition tn ansients with the exception of a spurious actuation of full flow from a HPSI pump. Overpressurization due to this transient will be precluded for temperatures 355'F and less by disabling l

two HPSI pumps, placing the third in pull-to-lock, and by throttling the third pum) to less than or equal to 200 gpm flow when it is used to add l

l mass to tie RCS.

Note that only the design bases events are discussed i.. detail since the less severe transients are bounded by the RCP start an4 inadvertent HPSI actuation analysis.

RCS temperature, as used in the applicability statement, is detennined as follows:

(1) with the RCPs running, the RCS cold leg temperature is the a)prosriate indication, (2) with the Shutdown Cooling System in operation, t1e slutdown cooling temperature indication is appropriate, (3) if neither the RCPs or shutdown cooling is in operation, the core exit thennocouples are the appropriate indicators of RCS temperature.

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3/4.4.10 STRUCTURAL INTEGRITY The inspection programs for the ASME Code Class 1, 2, and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant. To the extent applicable, the inspection program for these components is in compliance with Section XI of the ASME Boiler and Pressure Vessel Code.

3/4.4.11 CORE BARREL MOVEMENT _

This specification is provided to ensure early detection of excessive core barrel movement if it should occur.

f. ore barrel movement will be detected by using four excore neutron detectors to obtain Amplitude Probability Distribution (APD) and Spectral Analysis (SA). Baseline core l

barrel movement Alert Levels and Action Levels will be confinned during l

each reactor startup test program following a core reload.

Data from these detectors is to be reduced in two fonns.

Root mean square l

(RMS) values are ;omputed from the APD of the signal amplitude. These RMS magnitudes include variations due both to various neutrenic effects and internals motion. Consequently, these signals alone can only provide a gross measure e

.m harrel motion. A more accurate assessment of core barrel mottor 's wtained from the Auto and Cross Power Spectral Densities (PSD, XPSD), rase (6) and coherence (COH) of these signals. These data result from the SA of the excore detector signals.

A modification to the required monitoring program may be justified by an analysis of the data obtained and by an examination of the affected parts l

during the plant shutdown at the end of any fuel cycle.

CALVERT CLIFFS - UNIT 1 B 3/4 4-10 AmendmentNo.A77

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INSERT E (new paragraph for BASES 3/4.4.9)

[;

The allowed out-of-service times for degrad :.]Jow temperature overpressure prote: tion system in Modes 5 and 6 are based on~the cuidance provided in Generic Ixtter 90-06 and the time recuired to mnduct a controlled. deliberate cooldown. and to depressurire and vent the reactor coolant system n nder the Action statement entiv conditions.

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~ ATI'ACHMEN 2 UNIT 2 REVISED I

TECIINICAL SPECIFICATION

,2 AND BASES PAGES i

CIIANGE NO.1 3/44-7 H3/4 4-2 CIIANGE NO. 2 3/4 4-32'-

3/4 4 3/4 4 B3/4 410

. 1;;.

-NOTE:T n the INSERTS, wording which is a change from I

the current Technical Specifications is underlined.

..i:

a 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.3:

RELIEF VALVES LIMITING CONDITION FOR OPERATION-3.4.3.xTwo power-operated relief-valves (PORVs) and their associated block valves shall be OPERABLE.'

' APPLICABILITY: KET$ 1, 2, and ACTION *-

cekccQ nsaTA WP 2.

With aae er e : PORY(:) insper able, within L hour eitner restore the-POD.Y(+) te OP=d status or close Ine associsi.ed bicek valve (s) :nd vs. eve pe.er few i.ne biod vaive(s); olhenvise, be-in-at leert NOT STf_^:::Y -ithiri the i.ed 6 iivurs erd in-C0ED SNUTDOWN-wMhin. the 411ewinC 30 50;rs.

5.

With n; er r e ble:k valve (s) inep;r: bit, with" I heer ither restere the bleek V:1v (:) t: SPEP_^3LE :tstus er m ce t.be 1,leck valve (5) and...ov; ;:nt-4pom-th; bicek valve (s), eth:. ize, te, in at 12:3t "0T ET?."95Y rithin the next 6 he"*s eaa in entn-

• "iT~~yithin ing 30 heer-

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With en; er ier; bleek valve (:) :100 d and sewer Tr ved fra '

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$URVEILLANCE REQUIREMENTS 14.4.3.1 Each PORY shall be demonstrated OPERABLEi

a. At least once per 31 days by-performance of a CHANNEL TUNCTIONAL TEST, in accordance with Table 4.3-1 Item 4.

b. : At least once per 18 months by performance of a CHANNEL CALIBRATICN.

4/ T.2 -Each block valve shall be demonstrated 0PERABLE _at least once p f

yp Attqgh

.mgien.: n, r-s ggcomplete cycle.of full e

.. block valve is closed

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m er r m ved o mee pec cat on bTb.

'Isemecis cp A:+ionog b., cec. is

,C Add ZAbsE4I 3

. CALVERT CLIFFS - UNIT 2 3/4 4-7 AmendmentNo.gg

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- INSERT A (for Technical Specification 3.4.3 Actions)

- a.

If one or b_olh PORV(s) has excessive seat leakace, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> close the associated block valve (s) and maintain power to the block valve (s).

b.

With one PORV inoperable due to causes other than excessive PORV seat leakace. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 5 days or be in HOT STANDBY within the next R hours and at at elow 305'F b

within the following M hours, c.

'With both PORVs inonciable due to causes other than excessive PORV seat leakace within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORVs to OPERABLE status or close its associated block valve and remove nower from the block valve: restore one PORV to OPERABLE status within the followine 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and at or below 305'F within the followinE24 hours.

d.

' With one or both block' valve (s) inoperable, within -1 hour restore 'the block valve (s) to OPERABLE status or place its associated PORV(s) in override closed. Restore at least one block valve to OPERABLE status within the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if both block valves are inone able: restore any remainine inonerable block valve to OPERABLE status within the followine 5 days; otherwise,- be in at least HOT STANDBY within the next H hours and at or -

- below 305'F within the following M hours.

l INSERT B (for Technical Specification 3/4.4.3)

Above 305'r. At or below 305'F. Snecification 3/4.4.9.3 applies.

3/4.4 REACTOR COOLANT SYSTEM BASES shutdown cooling loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 psia.

The combined relief capacity of these valves is sufficient to limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss of turbine generator load while operating at RATED THERMAL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is taken for a direct reactor trip on the 'oss of turbine) and also assuming no operation of the pressurizer power-operated relief valve or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during shutdown and will be perfomed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Vessel Code.

3/4.4.3 RELIEF VALVES The power-operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the pressurizer code safety valves. These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emergency payMeu @ nsg e tb ityJ;oJAALthi possible RCS 1eakage path. 46u>eveQ4. h4h oneo J@e cdcey do M 3'# *"1 Og s

TuStWTON a s&h BelahD heGe4 a% desc+oor, & bol N,'*d f

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3/4.4.4 PRESSURIZER eme.egeq pe eq pac /- # f6/4 opeoW 6t/ Repde'ne A steam bubble in the pressurizer with the level as programed ensures that the RCS is not a hydraulically solid system and is capable of accomodating pressure st.rges during operation. The operating band for pressurizer level bounds the programed level and ensures that RCS pressure remains within the bounds of an analyzed condition during the excessive charging event as well as during the limiting depressurization event, Excess Load.

The operating band also protects the pressurizer code safety valves and power-operated relief valve against water relief. The power-operated relief valves function to relieve RCS pressure during all design transients.

Operation of the power-operated relief valve in conjunction with a reactor trip on a Pressurizer-Pressure-High signal, minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.

The requirement that 150 kw of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during CALVERT CLIFFS - UNIT 2 B 3/4 4-2 AmendmentNo.hp

JESERT C (for BASES 3/4.4.3)

The block valves are exempt from the surveillance reauirements to evcle the valves when they have been closed to comply with the ACTION requirements. This precludes the need to cycle the valves with full system differential pressure or when maintenance is beint performed to restore an inoperable PORV to OPERABLE status.

Power is maintained to the bhmk valve when it is closed to control excessive PORV seat leakace.

This allows the PORV and block valve to remain operable should the PORV be needed to control reactor pressure and facilitate decav heat removal durine certain accident conditions. The removal of power from a closed block valve for a PORV inoperable due to causes other than excessive PORV seat leakace provides additional assurance that the block valve will not be inadvertently opened when the condition of the PORV is uncertain.

RCS temperature. as used in the annlicability statement. is determined as follows: (1) with the RCPs runnine. the RCS cold lec temperature (Tc) is the annrontiate indication. (2) with the Shutdown Cooling System in operation. the shutdown cooline temperature indication is appropriate. (3) if neither the RCPs or shutdown cooline is in operation, the core exit thermocouples are the

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approntiate indicators of RCS tem..erature.

The testine for transferrine motive and control power for the PORVs and block valves from the normal to emercency power hus is donc under Technical Specification 4.8.1.1.2.d.3.

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i, 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Overoressure Protection Systems LIMITING CONDITION FOR OPERATION 3.4.9.3 The following overpressure protection requirements shall be met:

a.

One of the following three overpressure protection systems shall be in place:

1.

Two power-operated r, lief valteL{E0.Jtys t

i etting of S 430 psiat or geht<*

xua ws opM 2.

A single PORY with a lift setting of < 430 psi Tn ibawhM a

Reactor Coolant System vent of 11.3 square inch, or b/och Alk p aos 3.

A Reactor Coolant System (RCS) vent t 2.6 square inches.

b.

Two high pressure safety injection (HPSI) pumps'shall be disabled by either removing (racking out) their motor circuit breakers from the electrical power supply circuit, or by locking shut their discharge valves.

The HPSI loop motor operated valves (MOVs)' shall be prevented c.

from automatically aligning HPSI pump flow to the RCS by placing their handswitches in pull-to-override.

d.

No more than one OPERABLE high pressure safety injection pump with suction aligned to the Refueling Water Tank may be useri to inject flow into the RCS and when used, it must be under manual control and one of the following restrictions shall apply:

1.

The total high pressure safety injection flow shall be limited to 5 210 gpm OR 2.

A Reactor Coolant System vent of 2 2.6 square inches shall exist.

APPLICABILITY: When the RCS temperature is 5 305 F and the RCS is vented to <-8 square inches.

Except when required for testing.

CALVERT CLIFFS - UNIT 2 3/4 4-32 Amendment No. 249

3/4.4 REACTOR C00LAKT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

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ACTION:

a.

With one PORY inoperable *, either restore the inoperable PORV to OPERABLE status within 5 days or depressurize and vent the RCS through a > 1.3 square inch vent (s) within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />; maintain the RCS in a vented condition until both PORVs have been mgg a restored to OPERABLE status, h With both PORVs inoperable, depressurize and vent the RCS through a 12.6 square inch vent (s) within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />; maintain the RCS in a vented condition until either one OPERABLE PORY and a vent of 1 1.3 square inches has been established or both PORVs have been restored to OPERABLE status.

Ddp In the event either the PORVs or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient and any corrective action necessary to prevent recurrence, og') With less than two HPSI pumps' disabled, place at least two HPSI pump handswitches in pull-to-lock within fifteen minutes and disable two HPSI pumps within the next four hours.

{.93' With one or more HPSI loop MOVs' not prevented from automatically aligning a HPSI pump to the RCS, imediately place the MOV handswitch in pull-to-override, or shut and disable the affected MOV or isolate the affected HPSI header flowpath within four hours, and implement the action requirements of Specifications 3.1.2.1, 3.1.2.3, and 3.5.3, as applicable.

With HPSI flow exceeding 210 gpm while suction is aligned to the

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RWT and an RCS vent of < 2.6 square inches exists, 1.

Imediately take action to reduce flow to less than or equal to 210 gpm.

2.

Verify the excessive flow condition did not raise pressure above the maximum allowable pressure for t'ie given RCS temperature on Figure 3.4.9-1 or Figure 3.4.9-2.

Except when required for testing, i

l CALVERT CLIFFS - UNIT 2 3/4 4-33 AmendmentNo.f,4[

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INSERT D (new Technical Specification 3.4.9.3 Action b) h.

With one PORV inoperable in Modes 5 or 6. cither restore the inoperable PORV to OPERABLE status within 24-hours. or depressurize and vent the RCS through a 21.3 square inch vent (s) within the next 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />; and maintain the RCS in this vented condition until both PORVs have been restored to OPERABLE status.

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_p 3/4.4' REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued) 3.

If a pressure limit was exceeded, take action in accordance with Specification 3.4.9.1.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS-4.4.9.3.1 Each PORV shall be demonstrated 0PERABLE by:

a.

Performance of a CHANNEL FUNCTIONAL TEST on the PORY actuation channel, but excluding valve operation, within-31 days prior to entering a condition in which the PORY is required OPERABLE and at least _once per 31 days thereafter when the PORY is required 0PERABLE.

b.

Performance of a CHANNEL CALIBRATION on the PORY actuation channel at least onc r 18 months.

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c. ': Verifying the PORY M

valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the eing used for overpressure protection.

d.

Testing in accordance with the-inservice test requirements pursuant to. Specification 4.0.5.

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4.4.9.3.2 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

• when the vent (s) is being used for overpressure protection.

4.4.9.3.3: All. high pressure safety injection pumps, except the above OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the motor circuit breakers have been removed from their electrical power supply circuits or by verifying their discharge valves are locked shut. The automatic opening ' feature of the high pressure safety

_ injection loop MOVs shall be verified disabled at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l Except when the vent pathway is locked, sealed, or otherwise secured in the open position, then verify these vent pathways open at least once per 31 days.

CALVERT CLIFFS - UNIT 2 3/4 4-34 Amendment No. M[

3/4.4 REACTOR COOLANT S)ST_Qi BASES Note that only the design bases events are discussed in detail since the -

less severe transients are bounded by the RCP start and inadvertent HPSI actuation analysis.

RCS temperature, as used in the applicability statement, is detennined as follows:

(1) with the RCPs running, the RCS cold leg temperature is the appropriate indication, (2) with the Shutdown Cooling System in operation, the shutdown cooling temperature indication is appropriate, (3) if neither b-the RCPs or shutdown cooling is in operation, the core exit thennocouples Md

< are the appropriate indicators of RCS temperature.

/4.4.10 STRUCTURAL INTEGRITY The inspection programs for the ASME Code Class 1, 2, and 3 components ensure that the structural integrity of these components will be mair.tained at an acceptable level throughout the life of the plant. To the extent applicable, the inspection program for these components is in compliance with Section XI of the ASHE Boiler and Pressure Vessel Code.

3/4.4.11 CORE BARREL MOVEMENT This specification is provided to ensure early detection of excessive core barrel mov mei.t if it should occur. Core barrel movement will be detected by using four excore neutron detectors to obtain Amplitude Probability Distribution (APD) and Spectral Analysis (SA).

Baseline core barrel moyen..nt Alert Levels and Action Levels will be confirmed during each reactor STARTUP test program following a core reload.

Data from these detectors is to be reduced in two fonns.

Root mean square (RMS) values are computed from the APD of the signal amplitude. These RMS magnitudes include variations due both to various neutronic effects and internals motion. Consequently, these signals alone can only provide a gross measure of core barrel motion. A more accurate assessment of core barrel motion is contained from the Auto and Cross Power Spectral Densities (PSD, XPSD), phase (ip) and coherence (C0H) of these signals. These data result from the SA of the excore detector signals.

A modification to the required monitoring program may be justified by an analysis of the data obtained and by an examination of the affected parts during the plant shutdown at the end of any fuel cycle.

CALVERT CLIFFS - UNIT 2 B 3/4 4-10 AmendmentNo.)Mf

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.6 INSERT E (new paragraph for BASES 3/4.4.9)

The allowed out of-sersice times for decraded low temperature overpressure protection system in Modes 5 and 6 are based on the cuidance provided in Generic Letter 90-06 and the time reauired to conduct a controlled. deliberate cooldown. and to depressurize and vent the reactor coolant system under the Action statement entry conditions, i

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