ML20236X108

Amend 90 to License DPR-54,changing Tech Specs 3.2.2 on Low Temp Overpressure Protection & 4.3.1 on Surveillance Requirements for Ventilation Sys in Nuclear Svc Electric Bldg

ML20236X108
Person / Time
Site:	Rancho Seco
Issue date:	11/13/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236X107	List: ML20236X105 ML20236X108 ML20236X111
References
NUDOCS 8712080428
Download: ML20236X108 (9)

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I ,g NUCLEAR REGULATORY COMMISSION

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? SACRAMENTO MUNICIPAL UTILITY DISTRICT

' DOCKET NO. 50-312

, RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE.

Amendment No. 90 License No. aPR-54

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

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated April 23, 1987 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 facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission, i i

C. There is reasonable assurance (1) that the activitics authorized by this amendment can be conducted without endangering the health and l safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; j i

D. The issuance of this amendment will not be inimical to the comon  !

defense and security or to the health and safety of the public; and a

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.  !

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!2. Accordingly;.the license 1s amended by changes to the Technical-Specifications as hindicated in the~ attachment to -thistlicense amendment, and paragraph 2.C.(2) of Facility' Operating License.No. DPR-54 is hereby amended,to readf as follows:.

(2)1TechnicalSpecifications

• The Technical Specifications contained in Appendices .

A and B, as revised through Amendment No. 90,. are hereby incorporated inlthe 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

, dWM Gedrgey ighton,.,D ector Project Directorate.V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the sechnical ,

,Sp:cif,1 cations LDate. of: Issuance: November 13, 1987

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November 13, 1987 ATTACHMENT TO LICENSE AMENDMENT N0. 90 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 3-17a 3-17a 3-18 3-18 3-18a 3-18a >'

3-18b 3-18c 4-91 4-91 A I

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RANCHO SECO UtJIT 1 TECHNICAL SPECIFICATIONS i

Limiting Conditions for Operation

3. 2. 2 .- The Low Temperature Overpressure Protection Systeu will require the following conditions:

3.2.2.1 LTOP will be manually enabled prior to the Reactor coolcnt system temperature dropping below 350'F during plant cooldown.

3.2.2.1.1 Manual enabling of LTOP shall be accomplished by placing the Key Select Switch for the EMOV to the " Low" position and by placing HV-21505 in the "Open" position.

3.2.2.2 All HPI Systems will be locked out whenever the RCS temperature is below 350'F. This shall be done by opening and tagging the circuit breakers for the four HPI Motor-0perateo Valves (Loop A: SFV-23809, SFV-23811; and Loop B: HV 23801, SFV-23812) with the valves in the closed

. position, except as specified below: l 3.2.2.2.1 During Makeup, Letdown and Purification System startup, any of the four HPI MOVs specified in 3.2.2.2 above, which are perfonning the required isolation function, may be individually opened as required to fill and vent the respective injection line subject to .

the conditions stated in 3.2.2.2.2 and 3.2.2.2.3 below:

3.2.2.2.2 All HPI-Hakeup puap breakers shall be racked out and tagged during the filling and venting specified in f 3.2.2.2.1.

• i 3.2.2.2.3 Only one of the four HPI MOVs specified in 3.2.2.2 above may be open at any one time, and it shall be closed and its breaker racked out and tagged upon .,

conpletion of its line's filling and venting {

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3.2.2.3 The makeup tank water level is to be less than 86 inches. l l

3.2.2.4 The pressurizer water level will be maintained at or below  !

220 inches at systen pressures above 100 psig and less than 275 inches for pressures less than or equal to 100 psig except during RCS filling and draining.

i 3.2.2.5 When the RCS temperature is below 350'F, the core flood .

tank discharge valves are closed and the circuit breakers i for the motor operators are racked out before the RCS pressure is decreased to 600 psig, except as speciffeo g below: l l

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3 s i Amendment No. E7,90 3-17a

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I RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Liuf ting Conditions for Operation 3.2.2.5.1 When the Core Flood Tank pressure is below 500 psig, the discharge valves shall be allowed to remain open or be opened.

3.2.2.6 When LTOP is required, only one HPI pump will be operated except during the transition of pumps that will supply Reactor Coolant Pump seals and makeup flow for the RCS.

Bases y.

The makeup and purification system and chemical addition systems provide control of the reactor coolant system boron concentration.1 This is nomally accomplished by using either the makeup pump or one of the two high pressure injection pumps in series with a boric acid pump associated with the concentrated boric acid storage tank. The alternate method of boration will be the use of the makeup or high pressure inj directly from the borated water storage tank.gction pumps taking suction.

The quantity. of boric acid in storage from either of the two above-mentioned sources is sufficient to borate the reactor coolant systen to a 1 percent subcritical margin in the cold condition (70F) at the worst time in core life with a stuck control rod assembly. The maximum required is the equivalent of 9586 gallons of 7100 ppm boron. This requirement is satisfied by requiring a minimum volume of 10,000 gallons of 7100 ppm in the concentrated borated acid storage tank during critical operations. The minimum volume for the borated water storage tank (390,000 gallons of 1800 ppi boron), as specified in section 3.3, is based on refueling volume requirements and easily satisfies the cold shutdown requirement. The specification assures that the two supplies are available whenever the reactor is critical so that a single f ailure will not prevent boration to a cold condition. The minimum' volumes of boric acid solution given include the boron necessary to account for xenon decay.

The primary method of adding boron to the primary system is to pump the concentrated boric acid solution (7100 ppu boron, minimum) into the makeup tank using the 50 gpm boric acid pumps. Using only one of the two boric acid pumps, the required volume of boric acid can be injected in less than 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The alternate method of addition is to inject boric acid from the borated water storage tank using the high pressure injection pumps.

l Amendment No. 29,0 B2,90 3-18 I

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TECHNICAL SPECIFICATIONS Limiting. Conditions for Operation '

, Bases (Continued)

Concentration of boron in the concentrated boric acid -storage tank may be-higher than the concentration which would crystallize ati ambient conditions.

For this reason and to ensure that a flow of boric acid is available when needed, this tank and Its associated piping will be kept above 70F (30F, above the crystallization temperature. for the concentration present). Once in the high pressure injection systera, the concentrate is suf ficiently v c11 mixed and diluted so that nomal system temperatures ensure boric acid solubility.-

' .The value of 70F is significantly above the crystallization temperature for a

- : solution containing 12,200 ppm boron.3 1

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The Low Temperature Overpressure Protection System (LTOP)' consists of both an

' active and a passive subsysten. The active subsystem utilizes the Electro Matic Operated Valve .(El10V) which provides overpressure protection du_ ring nomal plant operation. The EMOV actuation circuitry has been modified to low-temperature provide aThe operations. second setpoint low setpoint (500 is manually psig)at that enabled 350 is useu during*F by key-operated switch in the Reactor control Room. An alam will sound in the Reactor Control Room if the reactor coolant' pressure falls below 450 psig and the key-operated switch is not selected for low-temperature operation. After selection of low temperature operation, additional'alams will occur if either HPI pump. breaker is not racked out; if either Scal . Injection flow is

. greater than 42 gpm or makeup flow is greater than 135 gpm; if.HPI valves are not closed; and if the EH0V block valve HV-21505 is not open. . The passive subsystem is based on the plant design and operating philosophy that precludes hydrotests hthe plant from being in a water solid condition (except for system i a

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' Injection line filling and venting is accomplished without an energized  !

Makeup or High Pressure Injection pump. Nitrogen overpressure in the Makeup tank provides the motive force for fluid flow during this evolution. This  ;

nitrogen overpressure is limited procedurally to 30 psig, and mechanically to '

100 psig by the relief valve on the Makeup tank. This pressure clearly does not approach the EMOV low setpoint. ,

q The exception to core flood discharge valves being closed and their motor operator deenergized is based on the Core Flood Tank pressure being reduced ] '

to less than the EMOV low setpoint of 500 psig. Without the potential for RCS over closed. pressurization, the valve need not be administrative 1y required to be i This provides for other surveillance testing and maintenance on the i Core F7 ood System.

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h RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS =

Limiting Conditi_ons.for_ Operation The Rancho Seco Reactor Coolant system always operates with a steam or' gas space in the pressurizer; the. steam bubble is replaced with. nitrogen .during-plant cooldown when system pressure is reduced. The requirements for a , '

maximua pressurizer level provides for'a sufficient vapor space in the-pressurizer to retard the- rate of increase of RCS pressure, as compared to a water solid system for' all ' mass and heat input transients. . In this manner, .

the operator will have time to recognize that a pressure transient is' in

. progress and take action to mitigate the incident. For these reasons the pressurizer water level will be maintained at or below 220 inches at system

' pressures above 100 psig and less than 275 inches for system pressures le'ss than or equal to 100 psig.

when the RCS is being _ filled or drained.The only exception During the filling to these requirements process the wil pressurizer is filled with water up to the 320 inch level. The liigh Point' Vents are opened and nitrogen is injected'into the pressurizer hence forcing -

the coolant .into the' loops. Subsequently, the High Point Vents are ' closed, a steam bubble is drawn and the nitrogen is released through the; pressurizer vents. 'During the. draining process, the pressurizer is depressurized, the ~

High Point Vents and RCS Hot Leg Vents are opened thus reducing the. RCS to atmospheric pressure. The loop coolant level and pressurizer level . equalize at 320 inches and draining can then take place.

In' conjunction with the enablement of LTOP at 350*F and the subsequent restriction on pressurizer level, analysis has shewn that the HPI system is not needed when RCS temperature falls below 350*F. The requirement for a naxinua nakeup tank level linits the nass input available from the' tank should the makeup valve f ail open.

When LTOP conditions are required, only one of the two HPI pumps or the i makeup puap will be allowed to operate. Rancho Seco normally operates with '

the makeup pump supplying makeup ana seal injection. Should, in the unlikely event, degradation of this pump occur while in the LTOP mode, i_t would be necessary to start one of the HPI pumps before stopping the makeup pump.

This scenario would result in a brief overlap time period where an increase j in flow through the makeup line would occur. However, because the operator '

is aware of the LTOP conditions, it is expected that this brief transition stage would not significantly increase the level of the pressurizer arid the probability of an over-pressurization incident. i i

, .g o j Amendment No. 90 3-18b

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions. for Operation l .

i Separate power supplies are provided for the ENOV circuitry and LTOP alanas which alert the operator of an overpressurization everet so that a single ,

power source failure will not disable the ENOV and LTOP alarms. This assures

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the operator is alerted ~so he can take action to terminate an event even if j the EMOV is disabled. These alarms are high pressurizer level, high - high l

pressurizer level, and high makeup tank water level.  !

REFERENCES  !

i l'OSAR Subsections 9.2 and 9.3 2 USAR Figure 6.2-1 3 Technical Specification 3.3 i

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, ;;,jAmendment No. E/,90 3-18c l

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-RANCH 0.SECO UNIT:11 TECHNICAL SPECIFICATIONS-Surveillance Standards

.[ f4.31

' NUCLEARISER V ICE ELECTRICAL BUILDING- EMERGENCY HEATING VENTI 1

AIR. CONDITIONING.

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.. Applicability Applies to' the Nuclear Service Electrical Building (NSEB$ Heating Ventilation and Air. Conditioning.(HVAC) System components. .

E Objec tive - 4 1

~ To verify that this system and its components will be able to' perform theirt design functions.

, Specification

.4131.1 The:NSEB Emergency HVAC shall be:

A. Demonstrated operable at least once' per. 31 days by init1'a ting flow through the essential air handling unit.

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~1. Verify that the. air handling unit maintains a minimum' flow:

rate of 24,500 cfm.

2. Verify that the condensing unit is operational.

Bases Thel purpose of the! Emergency Nuclear: Service Electrical' Building HVAC is to D,

limit high temperatures,which the building- would be subjected to upon loss of.

nomal cooling.' The, high temperatures will. affect'the environmental -3 qualification of safety related electronic equipment housed within the NSEB.  ;)

which is 'used to support'the Control Room /TSC upon accident conditions. The system is designed with an air handling unit and a condensing unit.which are' q activated upon high' temperature signals.  !

Since this. system is not nomally operated, a periodic test is required to ensure its operability when needed. Monthly testing of this system will'show that the system is available for its safety action. During this test'the system will be observed for unusual or excessive noise or vibration when the

i. fan motors are running.- The minimum air flow of 24,500 cfm was selected to L l l limit the' temperatures in the building to 80*F maximum (with the exception of 1

, the cable shafts). i The system is automatically started when the temperature in the NSEB Switchgea'r Room exceeds 95 T, except upon loss of offsite power; in which cast, the system can be manually started by the operator.

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Amendment No. 58,90 4-91

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