ML20247K712

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Amend 105 to License DPR-54,clarifying Operational Mode of Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Train & Revising Surveillance Requirements & Frequency of Verifying Auxiliary Feedwater Sys Flow Path
ML20247K712
Person / Time
Site: Rancho Seco
Issue date: 05/23/1989
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247K709 List:
References
NUDOCS 8906010369
Download: ML20247K712 (10)
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NUCLEAR REGULATORY COMMISSION-

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-SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312

_ RANCH 0'SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 105 License No. DPR-54 1.

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

A.

The application for amendment by Sacramento Muaicipal Utility District (the licensee) dated October 7,1988, as supplemented November 18, 1988 and March 27, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The f acility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; i

C.

There is reasonable assurance (1) that the activities authorized by this anendment can be conducted without endangering the health and

' safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the i.ealth 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 applicabic requirements have been satisfied.

2.

Accordingly, the license is amended by changes to tha Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read os follows:

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(2)TechnicalSpecifications The Technical Specifications contained in Appendices

.A and B, as revised through Amendment No. 105 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 its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Georg9. Knight

. Director Project Directo ate V Division of Reactor Projects - 111, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: May23, 1989

4 ATTACHMENT TO LICENSE AMENDMENT NO.105 FACILITY OPERATING LICENSE N0. DPR-54 DOCKET NO. 50-312 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are. identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3-23 3-23 3-23a 3-23a 3-23b(newpage) 3-24 3-24 3-24a 3-24a 4-39 4-39 4-39a 4-39a i

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RANCHO SECO UNIT-1 TECHNICAL SPEC 8FICATIONS-Limiting Conditions for Operation-3.41 STEAM AND POWER CONVERSION SYSTEM Apol !. abili tv Applies to the operability of th'e turbine cycle during normal operation and-for the removal of decay heat.

Ob'iective To specify minimum conditions of the turbine cycle equipment necessary to assure the required steam relief capacity during normal operation and the capability-to remove decay heat from the reactor core.

Spgrification L

' 4.1 The reactor coolant system shall not be brought or remain above 280*F through HOT SHUTDOWN when irradiated. fuel is.in the pressure vessci

.l unless the following conditions are met:

l-4 A.

Capability to remove decay heat by use of two steam generators as,

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specified in 3.1.1.2.A.

B.

One atmospheric dump valve per steam generator shall be operable.

C..

A minimum of 250,000 gallons of water shall be available in the condensate storage tank.

D.

Two main steam system safety valves are operable per steam generator.

E.

Both auxiliary feedwater pumps are operable and both cross tie valves (HV-31826 and HV-31827) are-operable and four flow paths which include the following valve groups:

Flow path #1 - FV-20527 & HV-20581 Flow path #2 - FV-20531 & HV-20577 Flow path #3 - FV-20532 & HV-20582 Flow path #4 - FV-20528 & HV-20578 are operable except that:

Flow path #1 QB #2 may be inoperable and flow path #3 QR #4 may be inoperable.

F.

Both trains of main feedwater isolation on each main feedwater line are operable.

Four independent backup instrument air bottle supply systems for l

G.

ADVs, and MFH (including MFH startup valves) and AFH valves are operable.

With less than the above required components operable, be on decay heat cooling within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Amendment. No. 93.105 3-23

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.4.2 The reactor shall not enter or remain in the STARTUP through POWER OPERATION mode unless the following conditions are met:

A.

Capability to remove decay heat by use of two steam generators as specified in 3.1.1.2.

B.

One atmospheric dump valve per steam generator shall be operable

~th only one atmospheric dump valve operable, except thai e>

restore an '. m /sle valve for the other steam generator within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; (2) with no atmospheric dump valves operable, restore at least one inoperable valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

C.

A minimum of 250,000 gallons of water shall be available in the condensate storage tank except that with less than the minimum volume, restore the minimum volume within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D.

Seventeen of the eighteen main steam safety valves are operable except that with less than the minimum number of valves, restore the inoperable valve (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

E.

Four turbine throttle stop valves are operable except that with less than the minimum number of valves, restore the inoperable valve (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

F.

Both auxiliary feedwater pumps are operable and both cross tie valves (HV-31826 and HV-31827) are operable and four flow paths tehich include the following valve groups:

Flov path #1 - FV-20527 & HV-20581 Flo. p C #2 - FV-20531 & HV-20577 Flow path #3 - FV-20532 & HV-20582 Flow path #4 - FV-20528 & HV-20578 are operable except that:

(1) Hith one auxiliary feedwater pump inoperable QB both flow paths #1 and #2 inoperable QE both flow paths #3 and #4 inoperable, restore to o;:er0ble status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With one or both valve (s) in a flow path inoperable, restore (2) the inoperable valve (s) to operable within 7 days, or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Amendment No. 92,105 3-23a i

RANCHO TECO UNIT 1

. TECHNICAL SPECIFICATIONS Li mi ti ng. Condi ti on s. for Operati on -

(3) Hith one or both cross tie valve (s)-inoperable, restore to operable status or place the valve (s) in the open position within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 0B be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(4) With both' auxiliery feed pumps inoperable QB more than two flow paths inoperable, the reactor shall '

made subtritical within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the reactor shh. be on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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Amendment No.105 3-23b j

RANCHO SECO UNIT 1

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TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

.3.4.2 G.

Both trains of main feedwater isolation on each mein feedwater line are operable except that:

(1) Hith one main feedwater isolation train ir. operable, restore the train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(2) Hith both main feedwater isolation traios inoperable, the reactor shall be made subtritical within four hours and the reactor shall be on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

H.

Two independent backup instrument air bottle supply systems (one per steamline) for ADVs are operable except that:

(1) Hith one system. inoperable, restore the system to operable status within 7 days or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(2) Hith two systems inoperable, restore at least one system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in hot shutdown within the next'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With one system restored to operable status within-24 hours, follow 3.4.2.H.(1).

I.

Two independent backup instrument air bottle supply systems (one per feedwater line) for MFH (including MFH startup valves), and AFH control valves are operable except that with either one or both system (s) inoperable, restore the inoperable system (s) within 7 days or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and on decay heat cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Bases The feedwater. system and the turbine bypass system are normally used for decay heat removal and cooldown above 280*F. Main feedwater is supplied by If neither main operation of a condersate pump and main feedwater pump.

feed pump is available, feedwater can be supplied to the steam generators by an auxiliary feedwater pump.. Steam relief capability is provided the system's atmospheric dump valves.

The auxiliary feedwater system is designed to provide sufficient flow on loss of main feedwater to match decay heat plus Reactor Coolant Pump heat input to the Reactor Coolant System before solid pressurizer operation could occur.l4) l' i

I Amendment No. 31, 87, 93, 105 3-24 1

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation The 250,000 gallons of water in the condensate storage tank is sufficient to remove decay heat (plus Reactor Coolant pump heat for two pumps) for approximately 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

This volume provides sufficient water to remove the decay heat for approximately 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and to subsequently cool the plant to the DHR system pressure at a cooldown rate of 50*F/hr (1).

The' minimum relief capacity of seventeen steam system safety valves is 13,329,163 lb/hr.(2) This is sufficient capacity to protect the steam system under the design overpower condition of 112 percent.(3)

Both trains of main feedwater isolation on each main feedwater line are required to be operable. Train A of main feedwater isolation is comprised of main feedwater control valves, main feedwater block valves and startup control valves. -Train B of main feedwater isolation is comprised of the main feedwater isolation valves.

Four independent Class 1 backup air supply systems are provided to assure power available to certain air operated valves in the event of the loss of normal air' supply. One system supplies power for the HFW, (including HFH l

startup valve), and AFH control valves feeding the "A" OTSG; another system supplies power for same valves feeding the "B" OTSG. Two systems supply power for ADVs with one for the ADVs on,the "A" main steam line and one for the ADVs on the "B" main steam line.

Each system is sized to provide at least two hours of air supply.

REFERENCES i

(1) B and H Document 32-1141727-00, " Heat Removal Capability of SMUD CST " Harch 1984.

(2) USAR paragraph 10.3.4 (3) USAR Appendix 3A, Answer to Question 3A.5 (4) B and W Calculation 86-1167930, " Rancho Seco: AFH Hinimum Flow Analysis," (SMUD Calculation No. 2-FHS 10150)

Amendment No. 21, 87, 92, 105 3-24a l

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1 RANCHO SECO UNIT 1

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TECHNICAL SPECIFICATIONS Sur Oillance Standards 4.8 AUXILIARY FEEDWATER PUMP PERIODIC TESTING l

Aeolicability Applies to the periodic testing of the turbine and motor driven auxiliary feedwater pumps.

Obiettive To verify that the auxiliary feedwater pump and associated valves are operable.

Specification 4.8.1 Monthly on a staggered test basis at a time when the average Reactor Coolant System temperature is 2280*F, the turbine / motor driven and motor driven auxiliary feedwater pumps shall be operated on recirculation to verify proper operation.

Separate tests will be performed in order to verify the turbine driven capability and the motor driven capability of auxiliary feedwater pump P-318.

The monthly test frequency requirement shall be brought current within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the average Reactor Coolant System temperature is 2280*f for the motor driven pumps.

The turbine driven capability shall be brought current within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of obtaining 5 percent reactor power.

Acceptable performance will be indicated if the pump starts and operates for fifteen n'inutes at a flow rate sufficient to assure 475 gpm of flow to the steam generator at a discharge pressure sufficient to drive that flow through the most restrictive flow path to a single steam generator which is at a pressure of 1050 psig.

The monthly testing of the auxiliary feedwater pumps and valves shall be performed in accordance with the inservice inspection requirements of Specification 4.2.2.1.

4.8.2 At least once per 18 month.

l.

Verify that each automatic valve in the flow path actuates to its correct position upon receipt of each auxiliary feedwater actuation test signal.

2.

Verify that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actuation test signal.

4.8.3 Monthly, when the average Reactor Coolant System temperature is 2280*F, all auxiliary feedwater system valves in the flow path that are not locked, sealed, or otherwise secured in position are to be inspected to verify they are in the proper position.

Amendment No. 31, 76, 80, 93, 105 4-39

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

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Surveillance Standards 4.8.4 Following maintenance or surveillance performed pursuant to Specifications 4.8.1, 4.8.2, and 4.8.5, those auxiliary feedwater valves manipulated in the performance of the maintenance or surveillance shall be verified to be in the proper position.

4.8.5 Prior to startup following a refueling shutdown or any cold' shutdown of longer than 30 days duration, conduct a test to demonstrate that the motor-driven AFH pumps can pump water from the CST to the steam generator.

Bases The monthly test frequency will be sufficient to verify that the turbine / motor driven and motor driven auxiliary feedwater pumps are operable.

Verification of correct operation will be ruade both from the control room instrumentation and direct visual observation of the pumps.

The OPERABILITY of the auxiliary feedwater systerr ensures that the Reactor Coolant System can be cooled down to less than 305*F from normal operating conditions in the event of a total loss of off-site power.

Valves which are manipulated for maintenance or the performance of surveillance will be verified to be returned to the proper position upon their return to service. This provides a high confidence of AFH system operability and enhances the reliability of the AFH system by augmenting the periodic valve position verification.

The electric driven auxiliary feedwater pumps are capable of delivering a total feedwater flow of 475 gpm at a pressure of 1050 psig to the entrance of the steam generators.

The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 475 gpm to the entrance of the steam generators over the steam generator operating range of 800 psig to 1050 psig.

This capacity is utilized as analytical input to the Loss of Main Feedwater Analysis which is the design basis event for AFH flow requirements.

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Amendment No. 27, 76, 80, 93,105 i

4-39a j

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