ML20212K553

Amends 95 & 91 to Licenses DPR-29 & DPR-30,respectively, Incorporating Surveillance Requirements for RHR Vault Flood Protection Sys

ML20212K553
Person / Time
Site:	Quad Cities
Issue date:	08/11/1986
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212K557	List: ML20212K553 ML20212K575 ML20212K681
References
NUDOCS 8608220165
Download: ML20212K553 (20)

Text

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'o UNITED STATES

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8 NUCLEAR REGULATORY COMMISSION o

j WASHINGTON, D. C. 20555

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COMMONVEALTH EDIS0N COMPANY AND IOWA-ILLINDIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 OtlAD CITIES NUCLEAR POWER STATION,llNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.95 License No. DPR-99 1.

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

A.

The application for amendment by Comonwealth Edison Company (the licenseel dated March 22, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Conriission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endancering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's reculations; 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 Comission'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.R. of Facility Operating license No. DPR-29 is hereby amended to read as follows:

860E220165 860911 PDR ADOCK 05000254 P

PDR

r, 1

.a B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FORTHENUCLEARREGULATgRY ISSION

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John A. Zwolinski, Director BWR roject Directorate #1

^

Division of RWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 11, 1986

ATTACHMENT TO LICENSE AMENDMENT NO.95 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 indicatino the area of change.

REMOVE INSERT 3.5/4.5-8

-3.5/4.5-8 3.5/4.5-9 3.4/4.5-9

• 3.5/4.5-9a 3.5/4.5-16a 3.5/4.5-16a 3.5/4.5-17 3.5/4.5-17 3.5/4.5-18 3.5/4.5-18 3.5/4.5-19

• 3.5/4.5-19

• Pagination change only

i ItuAD-CITIES DPE-?9

2. The discharge pipe pressure for the

2. Following any period where the systems in Specification 3.5.G.1 LPCI ende of the nHR or core shall be maintained at greater than spray ECC5 have been out of 40 psig and less than 90 psig if service and drained for mainte-pressure in any of these systems is nonce, the discharge piping of less than 40 psig or greater than 90 the Inoperable system shall be psig, this condition shall be alarmed vented from the high point prior in the control room and inmediate to the return of the system to corrective action taken. If the dis-service.

I charge pipe pressure is not within l

these limits in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the

3. Whenever the HPCI or RCIC system occurrence, an orderly shutdown shall is lined up to take suction from be Initiated, and the reactor shall the torus, the discharge piping be in a cold shutdown condition with-of the HPCI and RCIC shall be in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter initiation.

vented from the high point of the system and water flow observed on a monthly basis.

4. The pressure switches which i

monitor the discharge lines and j

the discharge of the fill l

system pug to ensure that they are full shall be functionally tested every month and call-brated every 3 months. The pressure switches shall be set to alarm at a decreasing pres-4 sure of 1 0 psig and an in-creasing pressure of 1 90 psig.

H. Condensate Pump Room Flood Protection H. Condensate Pug Room Flood Protection

1. The systems installed to prevent or

1. The following surveillance mitigate the consequences of flooding requirements shall be observed to j

of the condensate pug room shall be assure that the condensate pump operable prior to. startup of the room flood protection is reactor.

operable.

I

2. The condenser pit water level switches

a. The piping and electrical shall trip the condenser circulating penetrations, bulkhead water pugs and alarm in the control doors, and submarine doors room if water level in the condenser for the vaults containing pit exceeds a level of 5 feet above the RHR service water pumps the pit floor. If a failure occurs in and diesel generator cooling one of these trip and alarm circuits, pumps shall br checked during the failed circuit shall be lanediately each operating cycle by pres-placed in a trip condition and reactor surlaing to 15 + 2 psig and operation shall be permissible for the checking for leaks using a following 7 days unless the circuit is soap bubble solution. The sooner made operable.

criteria for acceptance shall be no visible leakage through the soap bubble solution.

I rv

'3 '

Amendment No. 66, 3 5A.5-8 i

I

o 1

IlUAD-CITit5 DPR-;'9

3. If Specification 3 5.H.1 and 2 cannot

b. During each operating cycle, be met, reactor startup shall not the following flood pro-connence or if operating an orderly tection level switches shall shutdown shall be initiated and the be functionally tested to reactor shall be in a cold shutdown give the following control condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, room alarms:

1) turbine building equip-ment drain swap high level

2) vault high level

c. The RHR service water vault sump pug discharge check valves outside the vault shall be tested for integrity, j

using clean domineralized water, at least once per operating cycle.

d. The condenser pit 5-foot trip circuits for each channel shall be checked once a month. A logic system functional test shall be per-formed during each refueling outage.

l. Average Planar LHGR

1. Average Planar LNGR During steady-state power operation, the Daily during steady-state opera-i average linear heat generation rate tion above 25% rated thermal power, (APLHGR) of all the rods in any fuel the average planar LNGR shall be assembly, as a function of average planar determined, exposure, at any axial location, shall not exceed the maximum average planar J. Local LHGR LHGR shown in Figure 3 5-1. If at any time during operation it is determined Daily during steady-state power by normal surveillance that the limiting operation above 25% of rated value for APLHGR is being exceeded, thermal power, the local LHGR action shall be initiated within 15 shall be determined.

minutes to restore operation;to within the prescribed limits. If the APLHGR is I

not returned in within the prescribed I

limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown: condition with-in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall continue until reactor operation l

is within the presr,ribed limits.

I Amendment No. BI, 9 5 3 5/4.5-s t

i

. o.

QUAD-CITIES DPR-29 J. Local LNGR During steady-state power operation, the linear heat generation rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the maximum allwable LHGR. If at any time during operation it :s determined by normal surveillance that the limiting value for LHGR is being exceeded, action shal,1 be initiated within 15 minutes to restore operation to within the prescribed limits.

If the LHGR is not returned to P

3.5/4.5-9a Amendment No. jf, g g

QUAD-CITIE5 DPR-29 The watertight bulkhead and submarine doors and the penetration seals for pipes I

and cables penetrating the vault wells and ceilings have been designed to with-stand the maximum flood conditions. To assure that their Installation is adequate for maximum flood conditions, a method of testing each seal has been devised.

[

In order to test an electrical penetration or pipe seal, compressed air is I

supp11ed to a test connection and the space between the fittings is pressurized to approximately 15 psig. The outer faces are then tested for leaks using a soap bubble solution.

l r

1 Amendment No. ID, 9 5 3 5/4.5- %

o DPR-29 ItuAD-ClTits 1

in order to test the submarine doors, a test frame must be Installed around each door. The frame is then pumped to a pressure of approximately 15 psig and held to test for leaktightness. The watertight bulkhead doors are tested by pressurlaing the volume between the double gasket seals to approalmately 15 psig. The gasket seal area is inspected using a soap bubble solution. Each RHR service water vault contains a sump, which will collect any floor or equipment leakage Inside the vault. A sump pump will automatically start on high level in the sump, and will pump the water out of the vault, via 2 dis-charge check valves outside the vault to the service water discharge pipe.

A conposite sampler is located on the sung discharge line. A radiation monitor is also located on the service water discharge. The sung discharge water is not expected to be contaminated, and any in-leakage to the vault is prevented by 2 check valves. Surveillance of these check valves is performed each operating cycle to assure their Integrity. The previously Installed bed-plate drains to the turbine building equipment drain sung have been capped off permanently.

A level switch set at a water level of 6 inches is located inside each vault.

l Upon actuation, the switch alarms in the control room to notify the operator of trouble in the vault. The operator will also be aware of problems in the vaults / condensate pung room If the high-level alarm on the equipment drain sump is not terminated in a reasonable amount of time.

A system of level switches has been Installed In the condenser pit to Indicate and control flooding of the condenser area. The following switches are installed:

Level Function a.

I foot (one switch) alarm, low water level b.

3 feet (one switch) alarm, high water level c.

5 feet (two redundant alarm and circulating water switch pairs) pump trip Level (a) Indicates water in the condenser pit from either the hotwell or the circulating water system. Level (b) is above the hotwell capacity and Indicates a probable circulating water failure.

Amendmentlpe. 95 3 5/4.5-17 l

- - -. _ - -. - ~ - -

4 I

I i

gjaD CITIES DPR-29 Should the switches at levels (e) and.(b) fail or the operator fail to trip the circulating water pugs on alarm at level (b), the actuation of either level switch l

pair at level (c) shall trip the circulating water pugs automatically ano alarm in the control room. These redundant level switch pairs at level (c) are desiped and l!

installed to IEEE 279, " Criteria for Raclear Power Plant Protection Systems." As the circulating water pumps are tripped, either manually or automatically at level (c) of 5 feet, the maximum water level reached in the condenser pit skJe to puming will be at elevation 568 feet 6 inches elevation (10 feet above condenser pit floor elevation 558 feet 6 inches; 5 feet plus an additional 5 feet attributed to pug coastdown).

In oroer to prevent the Rm service water pung motors arsi diesel-generator cooling water pump motors from overheating a vault cooler is supplied for each pump. Each vault cooler is designed to maintain the vault at a maximum of 1050F temperature during operation of its respective pug. For example, if diesel generator cooling water pump 1/2-3903 starts, its cooler also starts and maintains the vault at 105 F by removing heat supplied to the vault by the motor of pump 1/2-3903. If, at the same time that pump 1/2-3903 is in operation, R$ service water pwap IC starts, its cooler will also start and compensate for the added heat s@ plied to the vmJ1t by the l

IC pump motor keeping the vault at 1050F.

Each of the coolers is supplied with cooling water from its respective pump's i

discharge line. After the water has been passed through the cooler it returns to its respective pump's suction line. The cooling water quantity needed for each cooler is l

approximately 1% to 5% of the design flow of the pugs so that the recirculation of this small amount of heated water will not affect pump or cooler operation.

Operation of the fans and coolers is required during shutdown and thus additional surveillance is not required.

I Verification that access doors to eacn vault are closed following entrance by personnel is covered by station operating procedures.

)

The LKR shall be checked daily to determine if fuel bumup or control rod movement has caused changes in power distribution. Since changes (kJe to burnup are slow and only a few control rods are moved daily, a daily check of power distribution is 2

l adequate.

Average Planar LMiR At core thermal power levels less than or equal to 22, operating plant experience j

and thermal hydraulic analyses indicate that the resulting average planar OCR is below the maximum average planar UCR by a considerable margin; therefore, evaluation j

of the average planar LHGR below this power level is not necessary. The daily requirement for calculating everage plant UCR above 22 rated thermal power is t

sufficient, since power distribution shifts are slow when there have not been significant power or control rod changes.

3.5/4.5-18 Amendment b. 9 5

QUAD CITIES DPR-29 Local LHGR Tne LHGR as a function of core height shall be checked daily during reactor operation at greater than or equal to 255 power to determine if fuel tNrnup or control rod movement has caused changes in power distribution. A limiting LER value is precluded by a considerable margin when employing any permissible control rod pattern below 25%

rated thermal power.

Mininum Critical Power Ratio (EPR)

At core therinal power levels less than or equal to 254, the reactor will be operating at mininum recirculation pump speed and the moderator void content will be very small. For all designated control rod patterns which may be esployed at this point, operating plant experience and thermal hydraulic analysis indicate that the resulting MCm value is in excess of requirements by a considerable margin. With this low void content, any inadvertent core flow increase would only place operation in a more conservative mode relative to MCm.

The daily reqJirement for calculating MCPR above 255 rated thermal power is sufficient, since power distribution shifts are very slow when there have not been significant power or control rod changes. In addition, the Kf correction applied to the LCD provides margin for flow increases from low flows.

t i

f 3.5/4.5-19 Amendment no. g, 9 5

t k, Otto P

o UNITED STATES

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NUCLEAR REGULATORY COMMISSION g

E WASHINGTON, D. C. 20555

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COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET N0. 50-765 OtJAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATINr, LICENSE Amendment No. 91 License No. DPR-30 1.

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

A.

The aoplication for amendment by Commonwealth Edison Comnany (the licensee) dated March 22, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Actl and the Conmission'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 (1) that the activities authorized and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissinn'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 3.B. of Facility Operatina License No. DPR-30 is hereby amended to read as follows:

.=

.?_

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 91, are herebv incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATO CO. ISSION k-]'

e 5

ilohn

. Zwolinski, Director BWR Prsiect Directorate #1 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications 4

Date of Issuance: August 11, 1986

ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. LPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removino the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal ;!nes indicating the area of change.

REMOVE INSERT 3.5/4.5-8 3.5/4.5-8 3.5/4.5-9 3.4/4.5-9

• 3.5/4.5-9a 3.5/4.5-15a 3.5/4.5-15a 3.5/4.5-16 3.5/4.5-16 3.5/4.5-17 3.5/4.5-17 3.5/4.5-18

• 3.5/4.5-18

• Pagination change only i

i

t 1

l QUAD-CITIES DPR-30

2. The discharge pipe pressure for the

2. Following any period where the systems in Specification 3.5.G.1 1,PCI sede of the RHR or core shall be meintained at greater than spray ECCS have been out of 40 psig and less than 90 psig, if service and drained for mainte-pressure in any of these systems is nonce, the discharge piping of less than 40 psig or greater than 90 the Inoperable system shall be psig, this condition shall be alarmed vented from the high point prior in the control room and Isumediate to the return of the system to corrective action taken. If the dis-service.

charge pipe pressure is not within these limits in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the

3. Whenever the HPCI or RCIC system occurrence, an orderly shutdown shall is lined up to take suction from be initiated, and the reactor shall the torus, the discharge piping be in a cold shutdown condition with-of the NPCI and RCIC shall be in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter Initiation.

vented from the high point of the system and water flow observed on a monthly basis.

4. The pressure switches which monitor the discharge lines and the discharge of the fill system pump to ensure that they are full shall be functionally tested every month and call-brated every 3 months. The pressure switches shall be set to alarm at a decreasing pres-sure of 3,40 psig and an in-creasing pressure of 1,90 psig.

i H. Condensate pump Room Flood Protection H. Condensate Pung Room Flood Protection

1. The systems Installed to prevent or

1. The followir.g surveillance mitigate the consequences of flooding requirements shall be observed to of the condensate pump room shall be assure that the condensate pump operable prior to startup of the room flood protection is reactor.

operable.

2. The condenser pit water level switches

a. The piping and electrical shall trip the condenser circulating penetrations, bulkhead water punos and alarm in the control doors, and submarine doors room if water level in the condenser for the vaults containing pit exceeds a level of 5 feet above the RHR service water pumps the pit floor. If a failure occurs in and diesel generator cooling one of these trip and alarm circuits, punes shall be checked during the failed circuit shall be Isenediately each operating cycle by pres-placed in a trip condition and reactor surizing to 15 + 2 psig and operation shall be permissible for the checking for leaks using a following 7 days unless the circuit is soap bubble solution. The sooner made operable.

criteria for acceptance shall be no visible leakage through the soap bubble solution.

)

T'

$1 Amendment No. 60, 3 5/4.5-8

~. -

1 QUAD-CITIES DPR-30

\\

3. If Specification 3.5.H.1 and 2 cannot

.b. During each operating cycle.

j be met, reactor startup shall not the following flood pro-commence or if operating an orderly tection level switches shall shutdown shall be Initiated and the be functionally tested to reactor shall be in a cold shutdown l ve the following control i

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

room alarms:

i

1) turbine building equip-ment drain sump high level

2) vault high level

c. The RHR service water vault sump pump discharge check valves outside the vault shall be tested for integrity.

using clean domineralized water, at least once per 1

operating cycle.

d. The condenser pit 5-foot j

trip circuits for each channel shall be checked once a month. A logic system functional test shall be per-formed during each refueling outage.

1. Average Planar LHCR I. Average Planar LHGR 1

i During steady-state power operation, the Daily during steady-state opera-average linear heat generation rate tion above 25% rated thermal power.

(APLNGR) of all the rods in any fuel the average planar LNGR shall be assembly, as a function of average planar determined.

exposure, at any axial location, shall not exceed the maximum everage planar J. Local LNGR LHCR shown in Figure 3 5-1. If at any l

time during operation it is determined Daily during steady-state power by normal survelliance that the limiting operation above 25% of rated value for APLHGR is being exceeded, thermal power, the local LHCR action shall be Initiated within 15 shall be determined.

minutes to restore operation to within the prescribed limits, if the APLHGR is not returned in within the prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition with-in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

- Amendment No. iBI, p 2

-v

- - ~ -

-,--4

2

.=

DPR-30 QUAD-CITIES J. Local LNGR During steady-state power operation, the linear heat generation rate (LHGR) of any rod in any fuel assembly at any axlat location shall not exceed the maximum allowable LMGR.

If at any time during operation it is determined by normal surveillance that the limiting value for LHGR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits.

If the LHGR is not returned to

~

Amendment No. AT, $1

l QUAD-CITIES DPR-30 The watertight bulkhead and submarine doors and the penetration seals for pipes l

and cables penetrating the vault wells and ceilings have been designed to with-stand the maximum flood conditions. To assuts that their Installation is adequate for maximum flood conditions, a method of testing each seal has been devised.

l In order to test an electrical penetration or pipe seal, compressed air is I

supplied to a test connection and the space between the fittings is pressurized to approximately 15 psig. The outer faces are then tested for leaks using a soap bubble solution, l

2 Amendment No. p, g 2 3.5/4.5-15a

DPR-30 QUAD-CITits in order to test the submarine doors, a test frame must be Instelled around each door. The f rame is then pumped to a pressure of approximately 15 esig and held to test for leaktightness. The watertight bulkhead doors are tested by pressurizing the volune between the double-gasket seals to approximately 15 psig. The gasket seal area is Inspected using a soap bubble solution. Each RHR service water vault contains a sep, which will collect any ficer or equipment leakage inside the vault. A suno pump will automatically start on high level in the sump, and will pune the water out of the vault, via 2 dis-charge check valves outside the vault to the service water discharge pipe.

A conposite sampler is located on the sung discharge line. A radiation monitor is also located on the service water discharge. The sung discharge water is not expected to be contaminated, and any in-leakage to the vault is prevented by 2 check valves. Surveillance of these check valves is performed each operating cycle to assure their Integrity. The previously Installed bed-plate drains to the turbine building equipment drain sump have been capped off permanently.

A level switch set at a water level of 6 Inches Is located inside each vault.

Upon actuation, the switch alarms in the control room to notify the operator of trouble in the vault. The operator will also be aware of problems in the vaults / condensate pun, room if the high-level alarm on the equipment drain sump is not terminated in a reasonable amount of time.

A system of level switches has been InstaIIed in the condenser pit to Indicate and control flooding of the condenser area. The following switches are installed:

Level Function a.

I foot (one switch) alarm. Iow water level b.

3 feet (one switch) alarm, high water level c.

5 feet (two redundant alarm and circulating water switch pairs) pune trip Level (a) Indicates water in the condenser pit from either the hotwell or the circulating water system. Level (b) is above the hotwell capacity and Indicates a probable circulating water failure.

I i

Amendment No.

33 3.5/4.5-16

t i

9JAD CITIES DPR-30 ShoJld the switches at levels (a) and (b) fall or the operator fall to trip the circulating water pumps on alarm at level (b), the actuation of either level switch pair at level (c) shall trip the circulating water sumps automatically and alarm in the control room. These redundant level switch pairs at level (c) are designed and installed to IEEE 279, " Criteria for POclear Power Plant Protection Systess." As the circulating water pgs are tripped, either annually or automatically at level (c) of 2

5 feet, the maxinum water level reached in the condenser pit dJe to punging will be at elevation 568 feet 6 incnes elevation (10 feet above condenser pit floor elevation 558 feet 6 inches; 5 feet plus an additional 5 feet attributed to pung coastdown).

In order to prevent the R$ service water pump motors and diesel-generator cooling water puno actors from overheating a vault cooler is supplied for each pump. Each 0

vault cooler is designed to maintain the vault at a maximum of 105 F temperature cering operation of its respective punp. For exanple, if diesel generator cooling water pump 1/2-3903 starts, its cooler also starts and maintains the vault at 1050F by removing heat supplied to the vault by the motor of pung 1/2-3903. If, at the same time that pump 1/2-3903 is in operation, Rm service water pump IC starts, its cooler will also start and compensate for the added heat supplied to the vault by the IC pung motor keeping the vault at 1050F.

Each of the coolers is supplied with cooling water from its respective pump's discharge line. After the water has been passed through the cooler it returns to its respective pump's suction line. The cooling water quantity needed for each cooler is approximately 1% to 5% of the design flow of the punps so that the recirculation of this small amount of heated water will not affect pump or cooler operation.

Operation of the fans and coolers is required during shutdown and thus additional surveillance is not required.

I verification that access doors to each vault are closed following entrance by personnel is covered by station operating procedures.

The LHGR shall be checked daily to determine if fuel burnup or control rod movement has caused changes in power distribution. Since changes dJe to burnup are slow and only a few control rods are moved daily, a daily check of power distribution is adequate.

Average Planar LFCR At core thermal power levels less than or equal to 255, operating plant experience and thermal hydraulic analyses indicate that the resulting average planar LH(R is below the anximum average planar LPCR by a considerable margin; therefore, evaluation of the average planar LtCR below this power level is not necessary. The daily regiirement for calculating average p'. ant LMR above 255 rated thermal power is sufficient, since power distribution shifts are slow when there have not been significant power or control rod changes.

3.5/4.5-17 f

Amenchent k.'

II l

I QuRD CITIES DFH-30 Local L WA The LHGR es a function of core height shall be checked daily during reactor operation at greater than or equal to 255 power to determine if fuel burnup or control rod

+

movement has caused changes in power distr 1Dution. A limiting LHGR value is precludeJ by a considerable margin when employing any permissible control rod pattern below 254 rated thermal power.

Minimum Critical Power Ratio (m)

At core thermal power levels less than or equal to 255, the reactor will be operating 14 mininum recirculation pung speed and the moderator void content will be very full. For all designated control rod patterns which may be amployed at this point, ccoting plant experience and thermal hydraulic analysis indicate that the resulting et:P rglue is in excess of requirements by a considerable margin. With this low void crAlent, any inadvertent core flow increase would only place operation _in a more conservative mode relative to K.PR.

The daily required for calculating EPR above 254 rated thermal power is sufficient, since power distribution shifts are very slow when there have not been significant power or ccrttrol rod changes. In addition, the Kr correction applied to the LCO provides margin for flow increases from low flows.

1 x

e' 3.5/4.5-18 Amendment 2. JJ, g y i

-y

-