Text

Amend 94 to License DPR-61,revising heat-up Rate Curve & Providing Larger Interval for Low Temp Pressurization Protection Sys to Be Placed in Operation
	ML20235J015
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/10/1987
From:	Thomas C; Office of Nuclear Reactor Regulation
To:	;
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ML20235J014	List: ML20235J012; ML20235J015; ML20235J018;
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	NUDOCS 8710010267
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/' @lic\ UNITED STATES

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y NUCLEAR REGULATORY COMMISSION WASH;NGTON, D. C. 20656 -

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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET N0. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-61

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

A. The application for amendment by Connecticut Yankee Atomic Power ,

Company (the licensee), dated June 1, 1987, complies with the standards and requirements of the' Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as !

set forth in 10 CFR Chapter I; B. The facility will opera.te 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 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.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. OPR-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 94, are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the

~ Technical Specifications.

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3. This license amendment is effective as of the date of its issuance. I FOR THE NUCLEAR REGULATORY COMMISSION Ga o Q$w Cecil 0. Thomas, Director l

Integrated Safety Assessment Project Directorate l Division of Reactor Projects 111/IV/V and Special Projects

Attachment:

j Changes to the Technical 4 Specifications Date of Issuance: September 10, 1987 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the capti.oned amendment number and contain marginal lines indicating the area of change. -

REMOVE INSERT 3-4 3-4 3-4c 3-4c Figure 3.4-8 Figure 3.4-8 3-8 3-8 3-10a 3-10a 3-10b 3-10b 4-4 4-4 I t

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With one or more block valve (s) imperable, with'in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block l

valve (s) to OPERABLE status or close the block valve (s) and remove power from

" the block valve (s); otherwise, be in at least, HOT STANDBY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months i and in COLD SHUTIDW within the following M hours.

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(7) The pressurizer shall be operable with'at least 150 KW of pressurizer heater capacity. The pressurizer. level shall be within + 5% of its 3 programed value during periods of~ normal i operation, l

a. With the pressurizer inoperable due to ~ k the inoperability of both energency !

power supplies to the' pressurizer heaters either restore the inoperable emergency l power supply within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least BOT STARDBY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOW vithin the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Vith the pressurizer othervise ]

inoperable, be in at least HOT STANDBY with the reactor trip breakers open l within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in the ROI SHUTDOW within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. During transient operations (startup, power level changes, trips, etc.) the pressurizer level may be outside the 5%

band for periods not to exceed one hour.

D. Each steam generator in a non-isolated reactor coolant loop shall be restored to operable status prior to increasing Tave above 200 F. When starting a reactor coolant pump, and the reactor coolant cold leg temperature in any non-isolated loop is at or below 315"F, the secondary water temperature of each non-isolated steam generator shall not be more than 200F higher than the water temperature of each of the non-isolated reactor coolant cold legs. '

E.

2 The RCS Overpressure Protection System (OPS) shall be in operation when the RCS temperature is below I 0 l 115 F unless the RCS is vented through a minimum '

opening of three (3) inches (nominal diameter) or l' ~

its equivalent. j If one or more of the relief trains is taken out of service and the RCS is not vented, i

the following actions shall be taken:

3-4 Amendment No. AZ. 94 9 _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _

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_ Basis:

i perin FDSA hourSection of saturated steam at the valve set po t

l fully 5.2.2' I coolant system, the residual heat removal' system can fr and thereby control system temperature and pressure.

were removed by any of the means available, the amount of steam wh !

could the be capacity.

valves' generated at safety val've relief pressure would be less than against overpressurization.One valve, therefore, provides adequate defense When the boron concentration of the reactor coolant system is to be )

changed, the reactor. the process must be uniform to prevent sudden reactivity Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or on ')

residual heat removal pump is running while the change is taking place.

residual heat approximately removal one-half hour. pump will circulate the primary system volume in

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All pressurizer code safety valves are to be in service priory to to criticalit permit the design relieving flow to occur if required.

Part C of the specification requires that a sufficient number of reactor coolant occurs. pumps be operating to provide core cooling in the event loss of flow discussed in FDSA Section 10.3.2.The flow provided in each case will k 3 fission products to the reactor coolant cannot occur.Therefore, cladding dam By limiting the temperature differential between the primary y and seconda be prevented by the RCS OPS (See Reference 1 in Specifications 3.4 s in conjunction with Administrative Controls, Code e ASME preve Section ill, Appendix G pressure temperature limits.

condition for which the LTOPS is designed to prevent is an inadvertent H pump actuation when the RCS temperature is below 3500F, Since the HPSI 22 EFPY is the heat-up curve, the temperature below must be operable is 3150F.

Reference (1) D. C. Switzer letter to A. Schwencer, dated September 7 1977 , .

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-s Amendment No. EE, @9* N ' M 94

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0 3.5 CHDtICAL AND VOIDME CO.TIROL SYSTEM Appitcabilityt Applies to the operational status of the chemical and volume control system.

Obj ec tiv e:

To specify those limiting conditions for operation of the chemical and volum'e control system which must be met in order to ensure safe reactor operation.

I Specification?" A.

I The reactor shall not be critical unless the following chemical and volume control system conditions are met:

(1) Either two charging pumps or the metering pump and one charging pump oper'able.

(2) TVo boric acid pumps or one boric acid pump and gravity fill line to metering pump operable.

(3) The boric acid tank shall contain at least 12,000 gallons of solution whose concentration shall be at least 8 percent boric acid, but not greater than 13: boric acid.

The tempera ture shall be 140*F or higher.

(4) Maint ena nc e , which requires draining of the boric acid mix tank, shall be allowed only when the plant is shut down and the reactor coolant system borated to 8:4k shutdown.

(5) System piping and valves operable to the extent required to establish two flow paths for boric acid injection to the reactor coolant sys t em .

(6) Valve EA-V-399 shall be locked open and shall not be closed except when the plant is shutdown and the reactor c oolant system borated to a K,ff of 0.92 or less.

B. A maximum of one centrifugal charging pump shall be operable whenever the temperature of one or more non-isolated RCS cold legs is less than or equal to 315 F and the RCS is not vented by a minimum opening of a 3-inch diameter.

Basis: The chemical and volume control syste= provides control of the reactor coolant system boron inventory. Either a 360 gpm charging pump or a 30 gym metering pump is capable of injection concentrated boric acid directly into the coolant system.

Approximately 10,000 gallons of the 8% solution boric acide are required to meet cold shutdown requirements. Thus, a minL=um of 12,000 gallons in the mix tank is specified. An upper ,

concentration ILmit of 13% boric acid in the mix tank is 2

specilted to maintain solution solubility at the specified lov t empera tu re limit of 140*F. Limits on draining the tank are I

specified to af ford opportunity for scheduled maintenance.

The eight perc en t ak shutdown is specified bef ore boric acid mix tank maintenance is undertaken to preclude a return to criticality under any circumstances, even fuel movement.

Amendment No. 22, 33, 94 s_a

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VALVE NO. LOCATION ACTION -

RH-MOV-22 Containment Valve locked in open ,

Sump position, circuit breaker Suction locked out during post-LOCA long term cooling phase.

SI-MOV-24 RWST line " Valve locked in open position, circuit breaker l

locked out whenever reactor critical.*

SI-FCV-875 HPSI mini- Valve blocked and locked

. flow line in open position whenever ,

reactor critical.

RH-MOV-874 RHR Valve locked in closed I recirculation position and circuit breaker locked open whenever reactor is critical and reactor coolant temperature is above 3500F.* .

) *Except as permitted by Technical Specification 4.3.

C. The following actions shall be taken to disable the High Pressure Safety injection Pumps whenever the RCS temperature is below 3150F and the RCS is not vented by a minimum opening of torce (3) inches (nominal diameter) or its '

equivalent.

l. De-energize the HPSI pumps by racking out the breakers and locking the cabinets.

2. Close and lock the HPSI pump discharge valves (SI-V-855A

& B).

C. The following actions sha!! be taken to disable one centrifugal charging pump whenever the RCS temperature is below 3150F and the RCS is not vented by a minimum opening of three (3) inches (nominal diameter) or its equivalent.

1. Place the control switch in the trip pullout position. ,

,s 2. Red tag the switch "DO NOT OPERATE".

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3-10a Amendment No. J ) , 7/// , 93.94

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. BASIS This specification assures that adequate emergency core cooling capacity is available whenever the reactor is critical. Based on the loss of coolant analysis, l melting of the cladding is prevented with only one high pressure safety injection '

pump and one low pressure safety injection (core deluge) pump in operation. i Additionally, during the post-LOCA recirculation phase, sufficient cooling exists with onif one charging one HPSI, and one BHR available.

Each of the two trains of einergency core coo, ling equipment includes these three pumps. With the pu i associated with both trains of emergency core cooling equipment i substantial margin exists whenever normal power supplies or both diesel generatorsoperable are available. With only one diesel generator operating and the pumps associated with that diesel operable as required in Item (2) of Specification 3.12 the high pressure safety injection pump and the low pressure safety injection pump, would be started automatically. When the safety injection pumps are operating on off-site power, the charging pump would be started automatically. The RHR and char pumps would be available for manual start for long-term recirculation cooling. ging

- As described in Reference 3, the RCS OPS, in conjunction with administrative controls, prevents exceeding the temperature and pressure limits in Specification 3.4 while RCS temperature is under 315 0 F or the RCS is not vented.

Part C establishing limiting condition for operation regarding the disabling of the HPSI pumps to further assure that a pressure transient is' not initiated. Part D establishes requirements regarding the disabling of a charging pump to assure that y

a pressure transient is not initiated while retaining the flexibility to establish, under strict administrative controls, a redundant emergency boration path should such action be necessary.

FCV-796 is required to be throttled open within the range specified in and for the l reasons sited within References (6) and (7). That throttled position has been i

,' i determinedrecirculation.

post-LOCA by separate analyses to insure acceptable core performance during

REFERENCE:

. (2) FDSA Section 3.2.8 (3) D.C. Switzer (CYAPCO) letter to D.L. Ziemann (NRC),

dated May 22,1978.

(4) D.C. Switzer (CYAPCO) letter to D.L. Ziemann (NRC),

dated May 24,1978.

(5) D.C. Switzer (CYAPCO) letter to A. Schwencer (NRC),

dated September 7,1977 (6) E.3. Mroczka (CYAPCO) letter to C.I. Grimes (NRC), dated '

December 17,1986.

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q (7) E.3. Mroczka (CYAPCO) letter to C.I. Crimes (NRC), dated

] December 19,1986.

) x os Amendmentno.7/,/,se,n,94 l l .

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3; B). During normal operating periods, a manual test of all actuated

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components shall be conducted to demonstrate operability. The test shall be performed in accordance with written procedure as-summarized below: ,

1) Monthly, each of the high pressure safety injection pumps, each of the low pressure safety injection (core deluge) pumps, and each of .the residual heat removal (RHR) pumps shall be

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individually test run on recirculation.

. 2) Monthly, the charging pumps and metering pump shall be-individually test run.

3) At cold shutdowns all safety injection and core deluge valves will be cycled under "no-flow" conditions.

4) Monthly, each of the following valves will be exercised as indica ted.-

VALVE NO. LOCATION ACTION SI-MOV-24 RWST Line Moved manually from full open position approximately 1 inch of stem travel'and -

i- return to f ull open position to verify freedom of movement.

RH-MOV-874 RHR Recirculation Cycled fully from the full closed position to the full open position and back to the full closed position by use of the motor operator.

C) If one of the high pressure safety injection pumps or one of the low pressure safety injection (Core deluge) or one of the residual heat removal (RHR) pumps is out of service, the remaining pump shall be tested within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and at subsequent intervals of not greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

D) During each refueling shutdown, the remotely controlled, motor-operated containment spray water valve shall be operated under a "no-flow" condition. The test will be considered satisfactory if visual observation shows that the valve has operated satisf actority.

E) One centrifugal charging pump and the HPSI pumps shall be

demonstrated inoperable at least once per 31 days whenever the 3 temperature of one or more of the non-isolated RCS cold legs is less

, than or equal to 3250F and the RCS is not vented by a minimum opening of 3 inches, by verif ying that the charging pump control switch is in the trip pullout position and red tagged and that the HPSI breaker cabinets are locked and tagged out and the HPSI pump ,

discharge valves are locked closed.

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Amendment No J[ J7', ////, 94 m

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ML20235J015

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