ML20084R605

Amends 153 & 149 to Licenses DPR-29 & DPR-30,respectively, Changing TS by Revising Low Pressure Value at Which HPCI & RCIC Sys Can Be Tested to 150 Psig

ML20084R605
Person / Time
Site:	Quad Cities
Issue date:	05/30/1995
From:	Pulsifer R NRC (Affiliation Not Assigned)
To:
Shared Package
ML20084R608	List: ML20084R605 ML20084R641
References
NUDOCS 9506090347
Download: ML20084R605 (15)

Text

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UNITED STATES j

,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3066H001

/

COMMONWEALTH EDISON COMPANY A!m IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 OVAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. DPR-29 1.

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

I A.

The application for amendment by Commonwealth Edison Company (the licensee) dated April 10, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will-operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 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 i

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 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:

9506090347 950530 PDR ADOCK 05000254 i

p PDR

i

-l B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 153, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

i 3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION i

9

,9 Robert M. Pulsifer, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

-Specifications Date of Issuance: May 30, 1995 c

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ATTACHMENT TO LICENSE AMENDMENT N0.-153 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3.5/4.5-5

'3.5/4.5-5 3.5/4.5-6

3. 5/4. 5-6 3.5/4.5-7 3.5/4.5-7 3.5/4.5-8 3.5/4.5-8 3.5/4.5-23 3.5/4.5-23 3.5/4.5-24 3.5/4.5-24 4

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QUAD-CITIES DPR-29

4. Containment cooling spray loops are

2. During each 5-year period, an air required to be operable when the test shall be performed on the reactor water temperature is greater drywell spray headers and nozzles than 212*F and prior to reactor and a water spray test performed startup from a cold condition.

on the torus spray header and Continued reactor operation is nozzles.

permitted provided that a maximum of one drywell spray loop may be inoperable for 30 days when the reactor water temperature is greater than 2120F.

5. If the requirements of 3.5.B cannot be met, an orderly shutdown shall be initiated, and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. HPCI Subsystem C. HPCI Subsystem

1. The HPCI subsystem shall be operable Surveillance of HPCI subsystem shall whenever the reactor pressure is be performed as specified below with greater than 150 psig and fuel is in the following limitations. For item the reactor vessel.

4.5.C.3, the plant is allowed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in which to successfully

2. During startup following a refuel complete the test once reactor vessel outage or an outage in which work was pressure is adequate to perform each performed that directly affects HPCI test.

In addition the testing system operability, if the testing required by item 4.5.C.3.a shall be requirements of 4.5.C.3.a cannot be completed prior to exceeding 325 psig met, continued reactor startup is not reactor vessel pressure.

If HPCI is permitted. The HPCI subsystem shall made inoperable to perform overspeed be declared inoperable, and the testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to provisions of Specification 3.5.C.4 complete the tests before exceeding shall be implemented.

325 psig.

3. Except for the limitation of 3.5.C.2, Item Freauency if the HPCI subsystem is made or

1. Valve Position Every 31 days found to be inoperable, continued reactor operation is permissible only

2. Flow Rata Test-Every 92 days during the succeeding 14 days unless HPCI pump shall such subsystem is sooner made deliver at least operable, provided that during such 5000 gpm against 14 days the automatic pressure relief a system head subsystems, the core spray corresponding subsystems, LPCI mode of the RHR to reactor vessel system and the RCIC system are pressure when operable. Otherwise, the provision steam is being of Specification 3.5.C.4 shall be supplied to the implemented.

turbine at 920 to 1005 psig.

i i

3.5/4.5-5 Amendment No. 153

i QUAD-CITIES DPR-29

3. Flow Rate Test - During startup HPCI pump shall.

following a deliver at least refuel outage or 5000 gpm against an outage in a system head which work was corresponding to performed that i

reactor vessel directly affects pressure:

HPCI system

a. when steam operability.

is being supplied to the turbine at 150 to

-l 325 psig, and

b. when steam l

is being supplied to the turbine at 920 to 1005 psig.

4. If the requirements of Specification

4. Simulated Each refueling 3.5.C.1, 3.5.C.2 or 3.5.C.3 cannot be Automatic outage met, an orderly shutdown shall be Actuation Test initiated, and the reactor pressure shall be reduced to <150 psig within

5. Logic System Each refueling 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Functional Test outage.

D. Automatic Pressure Relief Subsystems D. Automatic Pressure Relief Subsystems Surveillance of the automatic pressure relief subsystem shall be performed as follows:

1. The automatic pressure relief

1. The following surveillance shall subsystem shall be operable whenever be carried out on a six-month the reactor pressure is greater than surveillance interval:

90 psig, irradiated fuel is in the reactor vessel and prior to reactor

a. With the reactor at pressure startup from a cold condition.

each relief valve shall be manually opened.

Relief valve

2. From and after the date that two of opening shall be verified by a the five relief valves of the compensating turbine bypass automatic pressure relief subsystem valve or control valve are made or found to be inoperable closure.

when the reactor is pressurized above 90 psig with irradiated fuel in the

2. A logic system functional test reactor vessel, reactor operation is shall be performed each refueling i

permissible only during the outage.

succeeding 7 days unless repairs are made and provided that during such time the HPCI subsystem is operable.

3 E 4.5-6 Amendment No.153

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QUAD-CITIES DPR-29 3.

If the requirements of Specification

3. A simulated automatic initiation 3.5.D cannot be met, an orderly which open; all pilot valves shall shutdown shall be initiated and the be performed each refueling reactor pressure shall be reduced to outage.

90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4. When it is determined that two valves of the automatic pressure relief subsystem are inoperable, the HPCI shall be demonstrated to be operable immediately.

E. Reactor Core Isolation Cooling System E. Reactor Core Isolation Cooling System

1. The RCIC system will be operable Surveillance of the RCIC system shall whenever the reactor pressure is be performed as specified below with greater than 150 psig and fuel is in the following limitations. For item the reactor vessel.

4.5.E.3, the plant is allowed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in which to successfully

2. During startup following a refuel complete the test once reactor vessel outage or an outage in which work was pressure is adequate to perform each performed that directly affects the test.

In addition, the testing RCIC system operability, if the required by item 4.5.E.3.a shall be testing requirements of 4.5.E.3.a completed prior to exceeding 325 psig cannot be met, continued reactor reactor vessel pressure.

If RCIC is startup is not permitted. The RCIC made inoperable to perform overspeed system shall be declared inoperable, testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to and the provisions of Specification complete the tests before exceeding 3.5.E.4 shall be implemented.

325 psig.

Item Freouency

1. Valve Position Every 31 days

2. Flow Rate Test - Every 92 days RCIC pump shall deliver at least 400 gpm against a system head corresponding to reactor vessel pressure when steam is being supplied to the turbine at 920 to 1005 psig.

3.5/4.5-7 Amendment No. 153

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QUAD-CITIES l'

DPR-29

3. Except for the limitations of

3. Flow Rate Test - During startup 3.5.E.2, if the RCIC system is made RCIC pump shall following a or found to be inoperable, continued deliver at least refuel outage reactor operation is permissible only 400 gpm against or an outage during the succeeding 14 days unless a system head in which work such system is sooner made operable, corresponding to was performed provided that during such 14 days the reactor vessel that directly HPCI system is operable. Otherwise, pressure:

affects RCIC i

the provisions of Specification

a. when steam system 3.5.E.4 shall be implemented.

is being operability, supplied to the turbine at 150 to 325 psig, l

and

b. when steam is l

l being supplied to the turbine at 920 to 1005 psig.

4. If the requirements of Specification

4. Simulated Each refueling 3.5.E.1, 3.5.E.2, or 3.5.E.3 cannot Automatic outage be met, an orderly shutdown shall be Actuation Test initiated and the reactor pressure shall be reduced to <l50 psig within

5. Logic System Each refueling 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Functional Test outage F. Minimum Core and Containment Cooling F. Minimum Core and Containment Cooling System Availability System Availability

1. Any combination of inoperable Surveillance requirements to assure components in the core and that minimum core and containment i

containment cooling systems shall not cooling systems are available have j

defeat the capability of the been specified in Specification remaining operable components to 4.2.B.

fulfill the core and containment l

cooling functions.

2. When irradiated fuel is in the i

reactor vessel and the reactor is in the cold shutdown condition, all low-i pressure core and containment cooling

(

systems may be inoperable provided no l

work is being done which has the potential for draining the reactor vessel.

3.5/4.5-8 Amendment No. 153

QUAD-CITIES DPR-29 4.5 SURVEILLANCE REQUIREMENTS BASES The testing interval for the core and containment cooling systems is based on a quantitative reliability analysis, judgment, and practicality. The core cooling systems have not been designed to be fully testable during operation. For example, the core spray final admission valves do not open until reactor pressure has fallen to 350 psig. Thus, during operation, even if high drywell pressure were simulated, the final valves would not open.

In the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable.

With a system, subsystem, loop or equipment out of service, overall core l

and containment cooling reliability is maintained by verifying the operability of the remaining systems, subsystems, loops or equipment. The l

verification of operability, as used in this context, for the remaining cooling systems means to administratively check by examining logs or other information to verify that the remaining systems are not out of service for l

maintenance or other reasons.

It does not mean to perform the surveillance requirements needed to demonstrate the operability of the remaining systems. However, if a failure, design deficiency, etc., causes the out-of-service period, then the verification of operability should be thorough enough to assure that a similar problem does not exist on the remaining systems.

For example, if an out-of-service period is caused by failure of a pump to deliver rated capacity due to a design deficiency, the other pumps of this type might be subjected to a flow rate test.

The surveillance requirements bases in this paragraph apply to all core and containment cooling systems except HPCI and RCIC. The systems can be automatically actuated during a refueling outage and this will be done. To increase the availability of the individual components of the core and containment cooling systems, the components which make up the system, i.e.,

1 instrumentation, pumps, valve operators, etc., are tested more frequently.

The instrumentation is functionally tested each month.

Likewise the pumps and motor-operated valves are also tested each month to assure their operability. The combination of a yearly simulated automatic actuation test and monthly tests of the pumps and valve operators is deemed to be adequate testing of these systems.

The surveillance requirements bases described in this paragraph apply only to the HPCI and RCIC systems. Following a refueling outage or an outage in

(-

which work was performed that directly affects system operability, the HPCI and RCIC pumps are flow rate tested against a system head corresponding to reactor vessel pressure, corrected for injection line losses, when steam is being supplied to the turbine at 150 to 325 psig, and again when steam is being supplied to the turbine at 920 to 1005 psig (rated reactor steam pressure). This combination of testing provides adequate assurance of pump performance throughout the range of reactor pressure at which it is required to operate.

The low pressure limit is selected to allow testing at a point of stable plant operation and also to provide overlap with low pressure ECC systems. A time limit is provided in which to perform the required tests during startop. This time limit is considered adequate to l

allow stable plant conditions to be achieved and the required tests to be performed. Flow rate testing of the HPCI and RCIC pumps is also conducted every 92 days against a system head corresponding to reactor vessel l

3.5/4.5-23 Amendment No. 153

QUAD-CITIES DPR-29 pressure, corrected for injection line losses, when steam is being supplied to the turbine at 920 to 1005 psig (rated reactor steam pressure), to demonstrate system operability in accordance with the LCO provisions and to meet inservice testing requirements for the HPCI system. Applicable valves are tested in accordance with the provisions of the inservice testing program.

In addition, monthly checks are made on the position of each manual, power operated or automatic valve installed in the direct flowpath of the suction or discharge of the pump or turbine that is not locked, sealed, or otherwise secured in position. At each refueling outage, a logic system functional test and a simulated automatic actuation test is performed on the HPCI and RCIC systems. The tests and checks described above are considered adequate to assure system operability.

The verification of the main steam relief valve operability during manual actuation surveillance testing must be made independent of temperatures indicated by thermocouples downstream of the relief valves.

It has been found that a temperature increase may result with the valve still closed.

This is due to steam being vented through the pilot valves during the surveillance test. By first opening a turbine bypass valve, and then observing its closure response during relief valve actuation, positive verification can be made for the relief valve opening and passing steam fl ow.

Closure response of the turbine control valves during relief valve manual actuation would likewise serve as an adequate verification for the relief valve opening. This test method may be performed over a wide range of reactor pressures greater than 150 psig. Valve operation below 150 psig is limited by the spring tension exhibited by the relief valves.

The surveillance requirements to ensure that the discharge piping of the core spray, LPCI mode of the RHR, HPCI, and RCIC systems is filled provides for a visual observation that water flows from a high point vent.

This ensures that the line is in a full condition.

Instrumentation has been provided on core spray and LPCI mode of RHR to monitor the pressure of water in the discharge piping between the monthly intervals at which the lines are vented and alarm the control room if the pressure is inadequate. This instrumentation will be calibrated on the same frequency as the safety system instrumentation and the alarm system tested monthly. This testing ensures that, during the interval between the monthly venting checks, the status of the discharge piping is monitored on a continuous basis. An alarm point of 40 psig for the low pressure of the fill system has been chosen because, due to elevations of piping within the plant, 39 psig is required to keep the lines full. The shutoff head of the fill system pumps is less than 90 psig and therefore will not defeat the low-pressure cooling pump discharge pressure interlock of 100 psig as shown in Table 3.2-2.

A margin of 10 psig is provided by the high pressure alarm point of 90 psig.

HPCI and RCIC systems normally take a suction from the Contaminated Condensate Storage Tanks (CCSTs).

The level in the CCST's is maintained at or above 3.5/4.5-24 Amendment No.153

/$

t UNITED STATES

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NUCLEAR REGULATORY COMMISSION

'2 WASHINGTON, D.C. 20eeH001 l

49.....,o t

COMMONWEALTH EDISON COMPANY E

i IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 i

OVAD CITIES NUCLEAR POWER STATION. UNIT 2 l

AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.149 f

License No. DPR-30 l

1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated April 10, 1995, complies with the standards and i

requirements of the Atomic Energy Act of 1954, as amended (the l

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 i

provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; j

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 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:

i

~

. B.

Technical Specifications-The Technical Specifications contained in Appendices A and B, as revised through Amendment No.149, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

i 3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION i

Robert M. Puls1fer, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 30. 1995 i

ATTACHMENT TO LICENSE AMENDMENT NO. 149 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3.5/4.5-4a 3.5/4.5-4a 3.5/4.5-6 3.5/4.5-6 3.5/4.5-15 3.5/4.5-15 1

l

e Guns-CITIES

_c BPR 30 4

C.

MPCI subsystem C.

W Cl Subs;l stem Surveillance of the MPCI subsystes shall be perfomed as specified below with the following itettattens. For item 4.5.C.3.

the plant is allemed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in which to successfully cesplete the test once reactor pressure is adeguate to perform each test.

In adottien, the testing reeutred by item 4.5.C.3.a shall be esspleted prior to exceeding 325 pois reactor vessel pressure.

If WCl ib made inoperable to perfom z

overspeed testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to couplete the tests before exceedthg 325 pets.

i lig Frecuency 2.

The WCI subsyste shall be operable 1.

Valve Positten Every 31 days whenever the reactor pressure is greater than 150 pstg and fuel is in the reactor vessel.

2.

During startup fellowing a refuel eutage er 2.

Flow Rate Test -

Every g2 days an outage in uhtch work was performed that WCl pump shall directly affects MPCI systen operability, deliver at least if the testing reeutronents of 4.5.C.3.a 5000 ppm against cannot be met, continued reactor startup is a systen head not pomitted. The WCl subsystem shall be corresponding to declared inoperable, and the provtsions of reactor vessel specification 3.5.C.4 shall be toplemented.

pressure when steam is being supplied to the turbine at g20 to 2005 pets.

3.

Except for the liettations of 3.5.C.2, if 3.

Flow Rate Test -

Ouring startup the MPCI subsystem ts made er found to be MPCI pap shall following a tnoperable, centinued reacter operation t deltver at least refueltng l

pereies1ble only during the succeerting 14 5000 spm ageinst outage or an days unless such subsystem is sooner made a systen head outage in operable, provided that during such 14 days corresponding which work was the automatic pressure reitef subsysten, to reactor perfomed that l

the core spray subsystens, LPCI mode of the vessel RHR systen, and the RCIC systen are directly pressure:

affects operable. Otherwise, the provistons of a.

When steam WCI system Specification 3.5.C.4 shall be implemented.

is being operability, supplied to the turbine at 150 l

l to 325 pstg, and b.

the steam is 1

being supplied l

to the turbine at g20 to 1005 psig.

4 If the requirements of Seecification 4

Staulated Automatic Each refueling 3.5.C.1, 3.5.C.2 er 3.5.C.3 cannot be set, Actuetten Test eutage an eroorly shutdown shall be initiated, and the reactor pressure shall be reduced to 5.

Logic Systen Each refueling e150 peig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Functtenal Test eutage 3.5/4.5-4a Amendment No. 149

.u OUAD-CITIES

-Opt-30 E.

Reactor Core isolatten Cooling System E.

Reactor Core Isolation Cooling System Surveillance of the RCIC system shall be perforend as specified below with thr following limitattens. For item 4.5.E.3.

the plant is alleued 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in which to-successfully cesplete the test once reactor vessel pressure is adequate to perform each test. In addition, the testing required by item 4.5.E.3.a shall be completed prior to escoeding 325 peig reactor vessel pressure.

If RCIC is ande inoperable to perform overspeed testing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to complete the tests before escoeding 325 peig.

lig Trecuency i

1.

The RCIC system will be operable whenever 1.

Valve Positten Every 31 days the reactor pressure is greater than 150 pstg and fuel is in the reactor vessel.

2.

During startup fo11 ewing a refuel eutage or 2.

Flow Rate Test -

Every p2 days i

an outage in which work was performed that RCIC pop shall directly affects RCIC system operability.

deliver at least if the testing requirenents of 4.5.E.3.a 400 gem against cannot be met, continued reactor startup is a system head not permitted. The RCIC systen shall be ceclared inoperable, and the provisions of corresponding to reactor vessel Specificatten 3.5.E.4 shall be implemented.

pressure when steam is being supplied to the turbine at p20 to 1005 psig.

3.

tacept for the Itaitations of 3.5.E.2. if 3.

Flow Rate Test -

During startup the RCIC system is unde or found to be RCIC pop shall following a inoperable, continued reactor operation is deliver at least refuel outage permitted only during the succeeding 14 400 gym against a or an outage days unless such system is sooner made system head in which work operable, provided that during such 14 days corresponding to was performed the HPCI system is operable. Otherwise, reactor vessel that directly the provisions of Specification 3.5.E.4 pressure:

affects RCIC shall be isolamented, system a.

When steam is operability, being suppiled to the turbine at 150 to 325 pstg, and b.

When steam is being supplied to the turbine at g20 to 1005 psig.

4.

If the reoutrements of Specification 4

Simulated Automatte Each refueling 3.5.E.1, 3.5.E.2 or 3.5.E.3 cannot be set.

Actuation Test outage an orderly shutdown shall be initiated and

+

the reactor pressure shall be reduced to 5.

Logic Systen Each refueling

<150 psis within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Functional Test outage 3.5/4.5-6 Amendment No. 149 1

I

i QUAD-CITIES DPR-30 4.5 SURVEILLANCE REQUIREMENTS BASES The testing interval for the core and containment cooling systems is based on a quantitative reliability analysis, judgment, and practicality. The core cooling systems have not been designed to be fully testable during operation. For example, the core spray final adnission valves do not open until reactor 2

pressure has fallen to 350 psig. Thus, during operation, even if high drywell pressure were simulated, the final valves would not open. In the case of the HPCI, automatic initiation during power operation would result in ptmping cold water into the reactor vesset, which is not desirable.

l With a system, subsystem, toop or equipment out of service, overall core and containment cooling reliability is maintained by verifying the operability of the remaining systems, subsystems, loops, or l

equipment. The verification of operability, as used in this context for the remaining cooling systems means to adninistratively check by examining logs or other information to verify that the remaining systems are not out of service for maintenance or other reasons. It does not mean to perform the surveillance requirements needed to demonstrate the operability of the remaining systems. However, if a failure, design deficiency, etc., causes the out-of-service period, then the verification of operability should be thorough enough to assure that a similar problem does not exist on the remaining systems. For examle, if an out-of service period is caused by f ailure of a ptmp to deliver rated capacity due to a design deficiency, the other pumps of this type might be subjected to a flow rate test.

The surveillance requirements bases in this paragraph apply to all core and containment cooling systems except HPCI and RCIC. The systems can be automaticatty actuated during a refueling outage and this will l

be done. To increase the availability of the individual components of the core and containment cooling systems, the conponents which make up the system, i.e., instrisnentation, ptsnps, valve operators, etc., are tested more f requently. The instrisnentation is functionalty tested each month. Likewise the pumps and motor-operated valves are also tested each month to assure their operability. The combination of a year'v simulated automatic actuation test and monthly tests of the ptsnps and valve operators is deemed to u adequate testing of these systems.

The surveillance requirements bases described in this paragraph apply only to the HPCI and RCIC systems.

l Following a refueling outage or an outage in which work was performed that directly affects system operability, the HPCI and RCIC pumps are flow rate tested against a system head corresponding to reactor vesset pressure, corrected for injection line tcsses, when steam is being supplied to the turbine at 150 to 325 psig, and again when steam is b=ing supplied to the turbine at 920 to 1005 psig (rated reactor steam pressure). This combination of testing provides adequate assurance of ptsnp performance throughout the range of reactor pressures at which it is required to operate. The low pressure limit is selected to allow testing at a point of stable plant operation and also to provide overlap with low pressure ECC systems. A time limit is provided in which to perform the required tests during startup. This time limit is considered adequete to allow stable plant conditions to be achieved and the required tests to be performed. Flow rate testing of the HPCI and RCIC ptsnps is also conducted every 92 days against a system head corresponding to reactor vessel pressure, corrected for injection line losses, when steam is being supplied to the turbine at 920 to 1005 psig (rated reactor steam pressure), to demonstrate system operability in accordance with the LCO provisions and to meet inservice testing requirements for the NPCI sys t em.

Applicable valves are tested in accordance with the provisions of the inservice testing program.

In addition, monthly checks are made on the position of each manual, power operated or automatic valve installed in the direct flowpath of the suction or discharge of the pwp or turbine that is not locked, sealed, or otherwise secured in position. At each refueling outage, a logic system functional test and a simulated automatic actuation test is performed on the HPCI and RCIC systems. The tests and checks described above are considered adequate to assure system operability.

The verification of the main steam relief valve operability during manual actuation surveillance testing must be made independent of temperatures indicated by thermocouples downstream of the relief valves. It has been found that a temperature increase may result with the valve still closed. This is due to steam being vented through the pilot valves during the surveillance test. By 1

1 3.5/4.5-15 Amendnent No. 149