ML20212N428

Amend 82 to License DPR-54,revising Tech Specs to Add Limiting Conditions for Operation & Surveillance Requirements for Low Temp Overpressure Protection Sys

ML20212N428
Person / Time
Site:	Rancho Seco
Issue date:	08/13/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212N414	List: ML20212N411 ML20212N428 ML20212N435
References
NUDOCS 8608280222
Download: ML20212N428 (11)

Text

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UNITED STATES y,

NUCLEAR REGULATORY COMMISSION 5

'N j WASHINGTON, D. C. 20555

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SACRA l1ENT0 MURICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-54 1.

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

A.

The application for amendment by Sacramento Municipal Utility District (the licensee) dated July 16, 1985, 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 e

forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasenable 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 +.he 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 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read as follows:

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Technical Specifications The Technical' Specifications centained in Appendices A and B, as revised through Amendment No. 82, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This licerse amendment is effective as of its date of issuance.

1 THE NUCLEAR REGUL TORY COMMISSION

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M.S[tol,

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irector i

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D ision of PWR Licen ing-B

Attachment:

Changes to the Technical j

Specifications Date of Issuance:

August 13,'1986 I

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I ATTACHMENT TO LICENSE AMENDMENT NO. 82 r

FACILITY OPEPATING LICENSE NO. 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

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and contain vertical lin~es indicating the area of change.

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3-17 3-17 I

3-17a 3-18 3-18 t

3-18a 4-7c 4-7c 4-8 4-8 i

4-8a 4-8a i

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RANCHO SECO UNIT &

TECHNICAL SPECIFlCATIONS TABLE OF CONTENTS (Continued)

Page Section 3-12 3.1.6 Leakage 3.1.7 Moderator Temperature coef ficient of Reactivity 3-15 3.1.8 Low Power Physics Testing Restrictions 3-15b 3-16 3.1.9 Control Rod Operation 3.2 HIGH PRESSURE INJEGTION, CHEMICAL ADDITION, AND LOW 3-17 TEMPERATURE OVERPRESSURE PROTECTION (LTOP) SYSTEMS 3,3-EMERGENCY CORE COOLING, REACTOR BUILDING EMERGENCY C0OLING, 3-19 AND REACTOR BUILDING SPRAY SYSTEMS 3.4 STEAM AND POWER CONVERSION SYSTEM 3-23 3.5 INSTRUMENTATION SYSTEMS 3-25 3.5.1 05eratienal Safety Instrumentation 3-25 3.5.2 Control Rod Group and Power Distribution Limits 3-31

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3-34 3.5.3 Safety Features Actuation System Setpoints 3.5.4 Incore Instrumentation 3-36 3.5.5 Accident Monitoring Instrumentation 3-38e 3.6 REACTOR SUILDING 3-39 i

3.7 AUXILIARY ELECTRICAL SYSTEMS 3-41 3.8 FUEL LOADING AND REFUELING 3-44 3.9 Deleted 1

3.10 SECONDARY SYSTEM ACTIVITY 3,47 3.11 REACTOR BUILDING POLAR CRANE AND AUXILIARY HOIST 3-49 l

i 3.12 SH0CK SUPPRESSORS (SNUB 8ERS) 3-51 l

3.13 AIR FILTER SYSTEMS 3-52 4

3.14 FIRE SUPPRESSION 3-53 3.14.1 Instrumentation 3-53 f

3.14.2 Water System 3-53 3.14.3 Spray and Sprinkler Systems 3-56 3.14.4 CO System 3-56 2

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Amendment No. 25, 3),gg, 82 ift

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.2 HIGH PRESSURE INJECTION, CHEMICAL ADDITION, AND LOW TEMPERATURE OVERPRE55uRE PNOTECTION (LTOP) SYSTEMS Applicability I

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Specification 3.2.1 applies to the operational status of the high pressure injection and chemical addition systems. Specification 3.2.2 applies to the operational status of the Low Temperature Overpressure Protection (LTOP)

System when the RCS temperature falls below 3500 F and the RCS is not open i

to atmosphere. Specification 3.2.2 is not applicable when the Reactor Vessel nead is removed, when any one of the 4 OTSG manways is open, when the pressurizer heater bundle is removed, or when the pressurizer manway is t

removed.

I Objective Specification 3.2.1 provides for adequate boration under all operating conditions to assure ability to bring the reactor to a cold shutdown condition. Specification 3.2.2 defines the necessary conditions for preventing an excessive overpressure transient to occur at low temperatures.

Specification 3.2.1 The reactor shall not remain critical unless the following conditions are met:

3.2.1.1 Two pumps capable of supplying high pressure injection are operable (also see Specification 3.3.2).

3.2.1.2 The borated water storage tank and its flow path to the reactor for high pressure injection are operable.

3.2.1.3 A source of concentrated boric acid solution in addition to the borated water storage tank is available and i

operable. This requirement is fulfilled by tne concentrated boric acid storage tank. This tank shall contain at least the equivalent of 10,000 gallons of 7,100 ppm boron. System piping and valves necessary to establish a flow path for high pressure injection shall also be operable and shall have at least the same temperature as the boric acia storage tank. One associated boric acid pump is operable. The concentrated boric acid storage tank water shall not be less than 70F, and at least one channel of heat tracing '

i shall be operable for this tank's associated piping.

The concentrated boric acid storage tank borgn concentration shall not exceed 8,500 ppm coron.

Amendment No. 27,67, 82 3-17

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RANCHO SECO UNIT 1 TECHN1 CAL SPEClFlCAT10NS Limiting Conditions for Operation 3.2.2 The Low Temperature Overpressure Protection System will require the following conditions:

I 3.2.2.1 LTOP will be manually enabled prior to the Reactor e

I Coolant System temperature dropping below 350*F during

' plant cooldown.

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 Dreakers for tne four HP1 Motor-Operated Valves (Loop A: SFV-23809, SFV-23811; ano Loop B: HV-23801, SFY-23812) with the valves in the closed position.

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

3.2.2.4 The pressurizer water level will be maintained at or below 220 inches at system pressures above 100 psig and less than 275 incnes for pressures less than or equal to 100 psig except durin'g RCS filling and draining.

3.2.2.5 The core flood tank discharge valves are closed and the circuit Dreaxers for the motor operators are racked out before the RCS pressure is decreased to 600 psig.

3.2.2.6 When LTOP is required, only c.1e HaI pump will be operated except during the transition of pumps that will supply Reactor Coolant Pump seals and makeup flow for the RCS.

Bases The makeup and purification system and chemical addition s control of the reactor coolant system boron concentration.gstems provide This is normally accomplishcc by using either the makeup pump or one of the two high pressure injection pumps in series with a beric acid pump associated with the concentrated boric scid storage tank. The alternate method of boration will be the use of the makeup or, high pressure injgetion pumps taking suction directly from the borated water. storage tank.

The quantity of boric acid in storage from either of the two above-mentioned sources is sufficient to boratt the reactor coolant. system to a 1 percent suberitical margin in the cold condition (70F) at the worst time ~in core life with a stuck control rod essembly. The maximuin required is the equivalent of i

9586 gallons of 7100 ppa boron. This requirement is satisfiec by requiring a minimum volume of 10,000 gallons of 7100 ppa in the concentrated borated acic 3-17a Amendment'No. 82

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation storage tank during critical' operations. The minimum volume for the borated i

water storage tank (390,000 gallons of 1800 ppm 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 failure will not prevent boration to a cold condition. The ain'imum 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 ppm boron, minimum) into the makeup i

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 in.iection pumps.

Concentration of baron in the concentrated boric acid storage tank may be higher than the concentration which would crystallize at 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 1

high pressure injection system, the concentrate is sufficiently well mixed and diluted so that normal system temperatures ensure boric acid solubility. The value of 70F is significantly above the crystallization temperature for a solution containing 12,200 ppm boron.

The Low Temperature Overpressure Protection System (LTOP) consists of both an active and a passive subsystem. The active subsystem utilizes the ElectrMatic Operated Valve (EMOV) which provides overpressure protection during nomal plant operation. The EMOV actuation circuitry has been modified to provide a second setpoint (500 psig) that is used during low-temperature operations. The low setpoint is manually enabled at 350*F by positioning a key-operated switch in the Reactor Control Room. An alarm 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 temjerature operation, additional alams will occur if either HPI pump breaker is not racked out; if either Seal Injection flow is greater than 42 gpm or makeup flow is greater than 135 gpm; if HPI valves are not closed; and if the EMOV block valve HV-21505 is not open. The passive subsystem is based on the plant design and operating philosophy that precludes the plant from being in a water solid condition (except for system hydrotests). 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 maximum. pressurizer level prcvides 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 3-18 Amendment No. 29, 69,82

RANCHO SECO UNIT 1 TECHN! CAL SPECIFICATIONS Limiting Conditions for Operation at system pressures above 100 psig and less than 275 inches for system pressures less than or equal 'to 100 psig. The only exception to these requirements will be when the RCS is being filled or drained. During the filling proce'ss the pressurizer is filled with water up to the 320 inch level. The High 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 releasec 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 shown that the HPI system is not needeo when RCS temperature falls below 350"F. The requirement for a maximum makeup tank level limits the mass input available from the tank should the makeup valve fail open.

When LTOP conditions are required, only one of the two HPI pumps or the makeup pump will be allowed to operate. Rancho Seco normally operates with the uakeup pump supplying makeup and seal injection. Should, in the unlikely event, degradation of this pump occur while in the' LTO? mode, it 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 in flow through the makeup line would occur. However, oecause the operator is aware of the LTOP conditions, it is expected tiist this brief transition stage would not significantly increase the level of the pressurizer and the probability of an over-pressurization incident.

Separate power supplies are provided for the EMOV circuitry and LTOP alarms i

which alert the operator of an overpressurization event so that a single power source failure will not disable the EH0V and LTOP alarms. This assumes the operator is alerted so he can take action to terminate an event even if the EMOV is disabled.

These alanos are hign pressurizer level, high - high pressurizer level, and high makeup tant water level.

REFERENCES 1

FSAR subsections 9.2 and 9.3.

2 FSAR Figure 6.2-1.

3 Technical Specification 3.3.

Amendment No. 82 3-18a I

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S Ebrtse a bMb Jrtbar abat aussJ TASLE 4.1-1 (Continued)

Surv2111anc2 Standards INSTRUMENT SURVEILLANCE REQUIREMENTS Channel Description Check Test Calibrate Remarks

57. Voltage Protection S(1)

(1) Compare voltmeter readings a.

Undervoltage M

R b.

Overvoltage M

R c.

Time Delay M

R

58. Containment Area High S

M (1)

R (1) Test using installed source l

Range Monitor

59. Nide Range Containment M

N/A R

Nater Level

60. Containment Hydrogen S

M Q

Analyzer

61. Emergency Sump Level M

N/A R

62. Containment Nide range M

.N/A R

Pressure Monitor / Recorder 4

63. High Range Noble Gas S

M R

Effluent Monitors

- RB Exhaust Stack

- Aux. Building Stack

- Radweste Vent

64. Main Steam Line Radiation S

M(1)

R (1) Test using installed source l

I Monitors

65. Subcooling Margin Monitors M

N/A R

66. Incore Thermocouples

'M N/A R

67. Low Temperature Over.-

N/A (1)

R (1) Prior to cooldown Pressure Protection (EMOV),

5 = Each shift M = Monthly P = Prior to each startup if not done previous week D = Daily Q = Quarterly R = once during the refueling interval W = Weekly

,5Y. Sesiannual 4

i, Amendment No, M, 99, 82 4-7c

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i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards MINIMUM EQUIPMENT TEST FREQUENCY Item Test Frequency 1.

Control rods Rod droD times of Each refueling shutdown all full length rods 2.

Control wd novemert Movement of each red Every two weeks 3.

Pressurizer code Setpoint Note 3 safety vr.1ves 4.

Main Steam safety Setpoint Note 3 valves 5.

Refueling system Functional Each refueling interval interlocks prior to handling fuel t

6.

Turbinest$nmstop Movement of each valve Monthly valves

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7.

Reactor Coolant Leakage Calculated inventory weekly System Leakage check daily 8.

Charcoal and high Charcoal and HEFA filter Each refueling interval and efficiency filters for iodine and particul-at any time work on filters ate removal efficiencies. could alter their integrity 00P test on HEPA filters.

Freon test on charcoal filter units.

-6 9.

Fire pumps and power Functional Monthly supplies

10. Reactor Building Functional Each refueling interval j

isolation trip

11. Spent fuel cooling Functional Each refueling interval system prior to fuel handling

12. Turbine Cverspeed Calibration Each refueling interval Trips

13. Internals Vent Manual Actuation. III Each refueling interval Valves Remott Visual inspec-tion.t2s and verify that valve not stuck open.

14. Reactor Coolant Functional test of Each refueling interval System High Point each valveI41 Vents III

15. Low Temperature Functional Prior to RCS temperature 0 F Overpressure decreasing below 350 Protection (EMOV) 08 l

Amendment No. 7,7),7%, W,82 l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

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Surveillance Standards TABLE 4.1-2 (Continued)

MINIMUM EQUIPMENT TEST FREQUENCY 1.

Verifying through manual actuation that the valve is fully open with a force of less than or equal to 400 lbs.

(applied vertically upward).

2.

Check visually accessible surfaces to evaluate observed surface irregularities.

3.

Tested in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50. Section 50.55a(g)(6)(i).

4.

Cycle each valve in the vent path through at least one complete cycle of full travel from the control room and verify the flow of gas through the system vent path. Verify all mar.ual isolation valves in each vent path are locked in the open position.

5.

EMOV block valve closed during test.

Amendment No. 7$ @9, 82 4-8a I

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