ML20002A858

Amend 58 to License DPR-28,revising Tech Specs to Authorize Replacement of Existing Pressure Switches That Sense Reactor Pressure & Water Level W/Analog Loops

ML20002A858
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	11/03/1980
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20002A860	List: ML20002A858 ML20002A865 ML20002A871
References
NUDOCS 8011210739
Download: ML20002A858 (29)

Text

- -. _ -.

UNITED STATES 3

NV: LEAR REGULATORY COMMISSION n

3 l

WASHWGTON, D. C. 20555

/

VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERM01T YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. DPR-28 l.

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

'A.

The applications for amendment by Vermont Yankee Nuclear Power Corporation (the licensee) dated March 17, 1980 and August 28, 1980, as supplemented May 9, August 13, September 23, and October 14, 1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, 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

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health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 4

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 Operating License No. DPR-28 is hereby amended to read as follows:

L Technical Specifications B.

The Technical Specii'ications contained in Appendix A, as revised 4

through Amendment No. 58, are hereby incorporated in the license.

The licensee shall operpte the facility jn a,ccordance with the Technical Specifications.

b 8 0112107M

2.-

. 3.

This license 'amendmant is effective as of-the date of its issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION 9

<. N

_ Thomas Ippolito, Chief -

-Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: November 3,1980 i

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'dTTACHMENT TO LICENSE AMENDMENT NO. 58

- FACILITY 0PERATING LICENSE NO. DPR-28

' DOCKET NO.'50-271' Review Appendix A as follows:

4 1.

Remove the pages-listed.and replace with identically numbered revised pages.

4 22 24 25 31 40 50 51 i.

52

-53 54 55-56 57 63

'135 i

136 174

' 176 4

178 179 l

2.

Add pages-34a, 39a, 53a, and 174a I

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VYNPS TABLE 4.1.1 SCRAM INSTRUMENTATION AND LOGIC SYSTl'3tS FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRU.s1ENTATION, LOGIC SYSTEMS AND CONTROL CIRCUITS 9

Instrument-Channel Group (3)

Functional TestU)

Minimum Frequency (4) 4' ode Switch in Shutdown A

Diace Mode Suitch in Shutdown Each Refueling Outage Manual Scram A

Trip Channel and Alam Every 3 Months Trip, Channc1 and Alarm (5)

BeforeEachStartupgWeekly

'IR11

. High Flux C

during refueling C

Trip Channel and AJ2rm Before Each Startu Weekly Inoperative during refueling APRM Trip Output Relays ((5)

Once Each Weck B

liigh Flux Trip Output Relays 5)

Before Each Startup Weekly liigh Flux (Reduced)

B" during refueling Inoperative B

Trip Output Relays Once Each Week Downscale B

Trip Output Relays (5 Once Each h'cck 5

Flow Bias B

Trip Output Reicys (g)

High Reactor Pressure a

Trip Channel and Alarm (5)

(1)

'l Illgh Dryuc11 Pressure A

Trip Channel and Alarm (1)

Low Reactor' Water Level B

Trip Channel and Alarm (5)

(I)

J High h'ater Level in Scram Discharge A

Trip Channel an'd.Alam Every 3 Honths

. Volume Trip Channel and Alarm (5)

Once Each Week High Main Steamline Radiation B

N in Steamline Iso. Valve Closure

'A

. Trip Ch'annel and Alarm-(1)

Turbine Ccn. Valve Fast Closure A'

Trip Channci and Alarm (1)

Turb'ine Stop Valve Closure A

Trip Channel and Alarm (1) 22 6 _+, o is c;o

VYNPS TABLS 4.1.1 NOTES Initially once per :nonth; tiicreafter, with en interval not 1 css then one month nor more than three The co=pilation of instruzent failure rate (.ata map include data obtained from othdr 1.

Doiling Water Recctors for }hich the scr.c design in..tru.-ent op: rates in an envircament similar to conths.

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- that of Vermont Yankec.

check chall be performed on reactor water level and reactor pressure instrumentation once per 2.

An instrument day and on steamline radiation monitors once per shift.

A descrintion of' the three groups is included in the basis of this Specification.

3.

runcticnal tests are not required when the systems are not rc'juired to be operable or are tripped.

If tcsts are missed, they shall be perfor:ned' prior to returning the systens to an operable status.

.4.

This Instrument This instrumentation is cy.capted from the Instru=cnt Functienal Test Definiti 5.

6.

Frequency need not exceed wcckly.

This coupled with placing A functional test of the logic of each channci is performed as indicated.

f the the code witch in shutdown c'ach refueling outage constitutes a logic system functional test o 7.

scrc3 system.

The water level ln the re' actor vessel will be perturbed and the corresponding Icvol indicator changes This tc.st will bc' performed every month after the completica of the monthly tests 8.

will be monitored.

i progran.

24 Amendment No. 58

VYNPS TABLE 4.1.2 2

SCRAM INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS Instrument Channel Croup (l)

Calibration Standard (4)

Minimum Frequency (2)

High Flux APRM Output Signal B

HeaB Balance Once Every 7 Days Output Signal (Reduced)

B Heat Balance Once Every 7 Days Flow Bias B

Standard Pressure 'and Voltage Source Refueling Outage APRM B(5)

Using TIP System Every 1000 equiv full pwr hr

- High Reactor Pressure B

Standard Pressure Source Once/ Operating Cycle l

Turbine. Control Valve Fast Closure A

Standard Pressure Source Every 3 months High Drywell Pressure A

Standard Pressure Source Every 3 months High Water Level in Scram Discharge Volume A

Water Level Herueling Outage Low Reactor Water Level B

Standard Pressure source Once/ Operating Cycle Turbine Stop Valve Closure A

(6)

Refueling outage High Main Steamline Radiation B

Appropriate Radiation Source (3)

Rerueling outage First Stage Turbine Pressure Permissive 4

Pressure Source Every 6 months and after refueling Maine Steauline Isolation Valve Closure A

(6)

Refueling outage I

Amendment No. 58 Page 25

VYNPS Bases:

4.1 REACTOR PROTECTION SYSTEM A.

The scram sensor channels listed in Tables 4.1.1 and 4.1.2 are divided into three groups: A, B and C.

Sensors that make up Group A are of the on-off type and will be tested and calibrated at the indicated intervals. Initially the tests are more frequent than Yankee experience indicates necessary.

However, by testing more frequently, the confidence level with this instrumentation will increase and testing will provide data to. justify extending the test intervals as experience is accrued.

Group B devices utilize an analog sensor followed by an amplifier and bi-stable trip circuit. This type of equipment incorporates local and/or control room mounted indicators and annu1ciator alarms. A failure in l

the sensor or amplifier may be detected by an als rm or by an operator who observes that one indicator doe's not track the others in similar channels. The bi-stable trip circuit failures'are detected by the periodic testing.

Group C devices are active only during a given portion of the operating cycle. For example, The IRM is active during start-up and inactive during full-power operation. Testing of these instruments is only meaningful within a reasonable period prior to their use.

B.

The peak heat flux and total peaking factor shall be checked once per day to determine if the APRM gains require adjustment. This will normally be done by checking LPRM readings.

Because few control rod movements or power changes occur, checking these parameters daily is adequate.

31 Amendment No. 58

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..j VYNPS I.~'

RECIRC PUMP TRIP INSTRUMENTATION I.

RECIRC PUMP TRIP INSTRUMENTATION 1

During reactor power operation, the Reciro Pump The Recire Pump Trip Instrumentation shall be Trip. Instrumentation shall be operative in functionally. tested and calibrated in accordance accordance with Table 3 2.1.

with Table 18.2.1.

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l 31 a Amendment No. 58

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VYNPS TABLE 3.2.1 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION Recirculation Pump Trip - A & B (Note 1)

Minimus Number of Operable Instrument Required Action When Minimum Channels per Trip' Conditions for Operation are System Trip Function trip Level Setting not Satisfied 2

Low-Low Reactor Vessel 6' 10.5" above top Note 2 Water Level of active fuel 2

High Reactor' Pressure 1.

1150 psig Note 2 2

Time Delays

<10 sec.

Note 2 1

Trip System Logic Note.2 Amendment No. 58 39a

4 VYNPS TABLE 3.2.1 NOTES 1.

Each of the two Core Spray, LPCI and RPT, subsystems are. initiated and controlled by a trip system. The subsystem l

"B" is. identical to the subsystem "A".

2..

If the minimum number of operable-instrument channels'are not available, the inoperable channel shall be tripped using test jacks or other permanently installed circuits.. If the channel cannot be tripped by the means stated above, that channel shall be made operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or an orderly shutdown shall be initiated'and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.. One trip' system with initiating instrumentation arranged in a one-out-of-two taken twice logic.

4 One trip system with initiating instrumentation arranged in a one-out-of two logic.

5.

If the minimum number of. operable channels are not available, the system is considered inoperable and the requirements of Specification 3.5 apply.

6.

Any one of the two trip systems will initiate ADS.

If_the minimum number of operable channels in one trip system is not available, the requirements of Specification 3.5.F.2 and 3.5 F.3 shall apply.

If the minimum number of operable channels is not available in both trip systems, Specifications 3.5.F.3 sha11' apply.

- 7.

One trip system arranged in a two-out-of-two logic.

Amendment No. 58

Y! HTS r

TABI.3 4.2.1

_ MINIMUM TEST & CAI.':tRATION FREOUENCIES EITRGENCY CORE C00LI!!C nCTUATION It!STRUMENTATIO!!

Core Spray Systect i

Trip Function-Functional Tes_t,(8)

Calibra ti_on (8)

Instrument Check t

High Drywell Pressure (Note 1) every 3 months Low-Iow Reactor Vessel (Note 1) once/ operating cycle once each day Water Level Low Reactor Pressure (Note 1) every 3 months Pu:ap 14-1A.- Discharge Press (Note 1) every 3 months

' Auxiliary Power Monitor (Note 1) every refueling once each day-Pu:ap Bus Power Monitor (Note 1) none once each day -

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High Sparger Pressure (Note 1) every 3 tenths Trip System Iagic every 8 months every 6 months except relays 14A-K11A (Note 2)

(Note 3) 14A-K11B 14A-K19A 14A-K19B Amendment No. 58 50 e

VYNPS TABLE 4.2.1 (Continued)

Lo Fressure Coclanc Iniaction Systc-n Calibration 40 Instrucent Check Function Test (S)_

Trio Function _

overy 3 :.:n:hr, Lou Reactor Pressure #1 (Note 1) every 3 conths (Note 1)

High Drywell Pressure #1 once each day l

once/oper'ating cycle

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Low-Lou Reactor vessel Water (Note 1)

Level every 3 months

. Reactor Vessel Shroud Level (Nota 1) every 3 months Low Reactor Pressure #2 (Note 1) every 3 months (Note 1)

Ri!R Pump Dischargefrcessure every 3 months (Nore 1)

High Dryucli Pressure #2 every 3 months Lo. Reactor Pressure #3 (Note 1) every refueling outage once each day Auxiliary Power Monitor (Note 1) once each day None (Note 1)

Punp Bus Power Monitor None' once each day

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LPCI Crosstie Monitor None.

Trip System Lcgic Every 6 Months every 6 months (Note 2)

(Note 3)

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51 Amendment No. 58

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VYNPS TABLE 4.2.1,(CONT) -

High Pressure Coolant Injection Syste:n

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Trip Function Functional Test (8)

Calibration (8)

Instrument Check l

ov-Low Reactor Vessel Water

-(Note 1) once/ operating cycle once each day Lev 21 Lsv Condensate Storage Tank (Note 1) every 3 months Ihtar Level

' High Drywell Pressure (Note 1)-

every 3 months W

High Suppression Chamber (Note 1) every 3 montha

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Water Level

- Bus Power Monitor

. (Note 1)

None once each day Trip System logic every 6 months every 6 months (Note 2)

(Note 3) 52 3

Amendment No. 58

i VYNPS TAB 1I 4.2.1 (CONT)

• Autornatic Depressur_ization System Trio Ftmetion Functional Test (8)

Calibration (8)

Instrument Check

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iLow-Low Reactor Vessel Water

.Leval (Note 1) once/ operating cycle once each day

!High Drywell Pressure (Note 1) every 3 months

Bus Power Monitors.

(Note 1) none once ' each

• day.

Trip 5/ sten logic every 6 months

'every 6 months (exc2pt solenoids of valves)

(Note 2)

(Note 3)

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Amendment No. 58 53 l

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VYNPS TABLE 4.2.1 (CONT)

Recirculation Pump Trip Actuation System Trip Function-Functional Test (8)

Calibration (8)

Instrument Check Low-Low Reactor (Note 1)

Once/ Operating Cycle Once Each Day Vesrol Water Level (%)

High Reactor

'(Note 1)

Once/ Operating Cycle Once Each Day

- Pre;Iure (%)

_ Note 1)

Once/ Operating Cycle

(

Trip System Logic i

s 1

53a Amendment flo. 58

VYNPS TABLE 4.2.2 MINIMUM TEST & CALIBRATION FREQUENCIES PRIltARY C0hTAIFMENT ISOLATION INSTRUt ENTATION_

Trip Function Functional Test (8)'

Calibration (8)_

Instrument Check once each day

. lev-Low Reactor Vessel Water once/ operating cycle (Note 1)

Level-

'High Steam Line Area each refueling (Note 1)

Teeperature outage Mgh' Steen Line F1'ov (Note 1) every 3 months onc'e each day Lee Main Steam Line Pressure (Note 1) every 3 months Lev Reactor Vessel Water

~~-

(Note 1) once/ operating cycle Lcvel High Main Steam Line Radiation (Notes 1 &'7) each refueling once each day outage (Note 1) every 3 months High Dryvell Pressure Cendenser Lov Vacuum (Note 1) every 3 months

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Trip System Logic every 6 months every 6 months except relays 16A-K13 (Note 2)

(Note 3) 16A-K14 16A-K15 16A-K10' 16A-K26 16A-K27 Amendment No. 58 5A

i VYNPS TABL E 4.2.2 (CONT'D)

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l_IINIHUM TEST:& CALIBRATION FREQUENCIES HIGH PRESSURE COOLANT TNJECTICN SYSTDI ISOLATION INSTRUMENTATION Trip Function Functional Test (8)

Calthra tion (8)

Instrument Check l.

High Reactor Water Level (Note 1)-

once/s erating cycle High Steam Lir.e Space Temperature

--(Note 1) each refueling outage Figh Steam Line d/p (Steam Lina Break)

Olote 11 every 3 months

. Low HPCI Steam Supply Pressure (Note 1) every 3 months Msin Steam Line Tu'unel (Note 1) each refueling Tecperature outage g

Bus Power Monitor (Note 1)

-None once cach day Trip System Logic every6conths every 6 months (Note 2) '

01ote 3)

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I Amendment No. 58

VYNPS TABLE 4.2.2 (CONT'D)

-HINIMUM TEST & CALIBRATION FREQUEMCIES RFACTOR CCRE TSOIATION COOLING SYSTEM ISOLATION INSTRUMENTATION-Trip Function Functional Test (8)

~ Calibration (8)

Instrument Check

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Main Steam Line Tunnel (Note 1) each refueling Tecperature outage High _ Steam Line Space (Note 1) each refueling Te:ap era ture outage High Steam Line d/p (Steam Line Break)

(Note 1) every 3 months High Reactor

• dater. Level (Note 1) once/ operating cycle l

Low RCIC Steam Supply Pressure (Note 1) every 3 months Bus Power Monitor (Note 1) none

' once each day 5

Trip System Logic every 5 months every 6 months

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(Note 2)

(Note 3) f 56

. Amendment.No. 58

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s VYNPS TABLE 4.2.3 MINDfUM TEST & CALT11 RATION FREQUENCIES REACTOR BUILDING VENTILATION & STi&DBY CAS TREATMENT SYSTEM ISOLATION Trip Function Functional Test (8)

_ Calibration (8)

Instrument Check

- Low Reaccor Vessel Water (Note 1)

once/ operating cycle Level-

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Iligh Dryvell Pressure (Note 1)

. ever'y 3 months Reactor Building Vent Exhcust Radiation Monthly every 3 months ence eacn day Refueling Flocr' Zone Monthly every 3 months once each day Radiation 1

9

.during 1:efueling

. Reactor Building Vent Trip System Logic

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every 6 months cvery 6 cienths (Note 2)

Note 3)

I' Standby Gas Treatment Trip System Logic every 6 months every 6 months (Note 2)

(Note 3)*

Logic Bus Power Honitor (Note 1) none once each day

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$7:

Amendment No. 58

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3 2 (Cont'd).

HO 4

The low-low reactor water level instrumentation'is set to trip when reactor water level is 6'10.5" or -44.52 2

indicated on the reactor water level instrumentation above the top of the active fuel. This trip initiates closure' of 4 ' "

the Group.1 primary containment isolation valves. and also activates the ECCS, RPT and starts the standby diesel generator system. This trip setting level was chosen to be low enough to prevent spurious operation but high enough to initiate ECCS operation, RPT and primary system isolation so that no melting of the fuel cladding will occur and so l

that post-accident cooling can be accomplished and the limits of 10 CFR 100 will not be violated. For the e,splete circumferential break of a 28-inch recirculation line and with the trip setting given above, ECCS initiation, RPT and primary system isolation are _ initiated in time to meet the above criteria. The instrumentation also covers the_ full range of spectrum of breaks and meets the above criteria.

The low low low reactor water level instrumentation is set to trip when the reactor water level has reached a level greater than two thirds of the core height. This value was selected as the minimum water level.in the reactor vessel, following a design basis accident, that emergency acore cooling system water can be diverted from its normal injection path, into the reactor vessel. At two thirds core height level and with high drywell pressure, the. appropriate valves may be manually operated to allow primary containment spray. operation.

The high drywell pressure instrumentation is a backup to the water level instrumentation and in addition to initiating ECCS it causes isolation of Group 2, 3, and 4 isolation valves. For the complete circumferential break discussed above, this instrumentation will initiate ECCS operation at about the same time as the low-low water level

, instrumentation; thus the results given above are applicable here also. Grcup 2 isolation valves include the drywell vent, purge, and sump isolation valves. High drywell pressure activates only these valves because high drywell pressure could occur as the result of non-safety related causes such as not purging the drywell air during startup.

Total system isolation is not desirable for these conditions and only the valves in Group 2 are _ required to close.

The water level instrumentation initiates protection for the full spectrum of loss-of-coolant accidents and causes a trip of all primary system isolation valves.

' Venturis are provided in the main steam lines as a means of measuring steam flow and also limiting the loss of mass inventory from the vessel during a steam line break accident. In addition to monitoring steam flow, instrumentation is provided which causes a trip of Group 1 isolation valves. The primary function of the instrumentation is to detect a break in the main steam line, thus only Group 1 valves are closed. For the worst case accident, main steam line break outside the drywell, this trip setting of 120 percent of rated steam flow in conjunction with the flow limiters and main steam line valve closure limit the mass inventory loss such that fuel is not uncovered, fuel temperatures remain less than 12950F and release of radioactivity to the environs is well below 10 CFR 100.

Temperature monitoring instrumentation is provided _in the main steam line tunnel to detect leaks in this area. Trips are provided on this instrumentation and when exceeded cause closure of Group 1 isolation valves. Its setting of ambient plus 950F is low enough to detect leaks of the order of 5 to 10 gpm; thus, it is capable of covering the entire spectrum of breaks. For large breaks, it is a backup to high steam flow instrumentation discussed above, and for small breaks with the resultant small release of radioactivity, gives isolation before the limita of 10 CFR 100 are exceeded.

63 Amendment No. 58 m

TABLE 4.7.2.0 PRIMARY C0ffrAlletENT ISOLATION VALVES VALVES SUBJECT TO TYPE C LEAKAGE TESTS Ioolation haber of Power h uimus Action on Operated Valves Operating Normal Initiating Group (Note 1)

Valve Identifiestion Inboard Outboard Time (Sec)

Position Signal

'I h in Steam Line Isolation (2-80A, D & 2-86A, D) 4 4

5(note 2)

Open CC i

1 Main Steam Line Drain (2-74, 2-77) 1 1

35 Closed SC 1

Recirculation Loop Sample Line (2-39, 2-40) 1 1

5 Closed SC 2

RHR Discharge to Radweste (10-57,10-66) 2 25 Closed

_ SC 2

Drywell Ploor Drain (20-82, 20-83) 2 20 Open GC 2

Drywell Equipment Drain (20-94, 20-95) 2 20 Open CC

,3 Drywell Air Purge Inlet (16-19-9) 1 10 Closed SC 1

Drywell Air Purge Inlet (16-19-8) 1 10 Open CC 1

Drywell Purge & Vent Outlet (16-19-7A) 1 10 Closed SC 3

Drywell Purge & Vent Outlet Bypass (16-19-6A) 1 10 closed SC s3 Drywell & Suppreselon Chamber Main Exhaunt (16-19-7) 1 10 closed SC 3

Suppression Chamber Purge Supply (16-19-10) 3 Suppression Chamber Purge & Vent Outlet (16-19-78) 1 10 Closed SC 1

10 Closed SC 3

Suppression Chamber Purge & Vent Outlet Bypass (16-19-68) 1 10 Open CC 3

Exhaust to Standby Cao Treatment System (16-19-6) 1 10 Open CC 3

Contairment Purge Supply (16-19-23) 1 10 Open CC 3

Containment Purge Makeup (16-20-20,16-20-22A,16-20-22b) 3 NA Clocad SC 5

Reactor Cleanup System (12-15,12-18) 1 1

25 Open CC 5

Reactor Cleanup System (12-68) 1 45.

Open CC l

6 HPCI (23-15, 23-16 1

1 55 Open CC l

6 RCIC (13-15,13-16) 1 1

20 Open CC Primary / Secondary Vacuum Relief (16-19-11A,16-19-118) 2 NA Closed SC Primary / Secondary Vacuum Relief (16-19-12A,16-19-12B) 2 NA Closed Process Control Rod Hydraulic Return Check Valve (3-181)

NA Open Process 3

Containment Air Sampling (VC 23, VC 26,109-76A&B) 4 5

Open CC i

1 I

135.

Amendment tio. 58 1

VTNPS i

P Table 4.7.2.b PRIMARY CONTAINMENT ISOLATION VALVES VALVES NOT SUBJECT TO TYPE C LEAKAGE TESTS Number of Power Maximus Actice os Isolation Operated Valves Operating Normal Initiating Group (Note 1)

Valve Identification Inboard Outboard Time (sec)

Position Signal 2

R 2 Return to Suppression Pool (10-39A,B) 2 70 Closed SC 2

RHR Return to Suppression Pool (10-34A,B) 2 120 Closed SC 2

kHR Drywell Spray (10-26A B & 10-31A,B) 4 70 Closed SC 2

RHR Suppression Chamber Spray (10-38A,B) 2 45 Closed SC

_3 Containment Air Compressor Suction (72-3BA,B) 2 20 Open CC i

4 RIDt Shutdown Cooling Supply (10-18, 10-17) 1 1

28 Closed SC I

4 RHR Reactor IIcad Cooling (10-32, 10-33) 1 1

25 Closed SC Feedwater Check Valves (2-28 A,B) 2 2

NA Open Proc.

Reactor Need Cooling Check Valve (10-29) 1 NA Closed Proc.

. Standby Liquid Control Check Valves (11-16, 11-17) 1 1

NA Closed Proc.

Hydrogen Monitoring (109-75 A,1-4; 109-75 E-D,1-2) 10 NA NA NA

. Sampling Valves - Inlet Hydrogen Monitoring (VG-24, 25, 33, 34) 4 NA NA NA

• These valves are remote manual sampling valves which do not receive an isolation signal.

Only one valve in each line is required to be operable.

Amendment No. 58 136

VYNPS o

3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEILLANCE REQUIREMENTS b.

The undervoltage automatic starting circuit of each disel generator shall be tested once a mor.th.

c.

Once per operating cycle, the actual conditions under which the diesel generators are required to start automatically w'ill be simulated and a test conducted to demonstrate that they will stI-t within 13 seconds and accept the emergency load and start each load within the specified starting time. The results shall be logged.

2.

Batteries 2.

Batteries The following battery chargers shall be operable:

a.

Four battery chargers for the + 24 a.

Every week the specific gravity volt neutron monitor and process and voltage of the pilot cell and radiation batteries.

temperature of adjacent cells and overall battery voltage shall be measured and logged, b.

Two of the three battery chargers b.

Every three months the voltage of for the 125 volt station batteries.

each cell to nearest 0.01 volt and specific gravity of each cell to the nearest 0.005 ap.gr. shall be measured and logged.

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c.

One of the two battery chargers c.

Once each operating cycle each for the 125 volt switchyard station 125 volt battery shall be batteries.

subjected to a rated loud discharge test. The specific gravity and voltage of each cell shall be measured after the discharge test and logged.

Amendment No. 58 174

4 4

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3.10 LIMITING CONDITIONS FOR OPERATION 4.10.

SURVEILLANCE REQUIREMENTS d.

Two of the' three battery chargers for the'24 volt ECCS Instrumentation.

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4 F

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' Amendment No. 58 i

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VYNPS 3.10 LIMITING ODNDITIONS POR OPERATION 4.10 SURVEILLANCE REQUIREMENTS B.

Operation with Inoperable Components B.

Operatiop with Inoperable Components Whenever the reactor is in Run Mode or Startup Mode with the reactor not in the Cold Condition, the requirements or 3 9. A shall be met except:

1.

Diesel Generators 1.

Diesel Generators From and after the date that one of the When it is determined that one of the diesel

. diesel generators or its associated buses generators in inoperable the requirements or are made or round to be inoperable for any Specification 4.5.H.1 shall be satisfied.

reason and the remaining diesel generator is operable, the requirements of Specification 3 5.H.1 shall be satisfied.

2.

Batteiles 2.

Batteries a.

From and after the date that Samples of the battery room atmosphere shall ventilation is lost in the battery be taken daily for hydrogen concentration room,' portable ventilation equipment determination.

shall be provided.

b.

From and after the date that one of the two 125 volt station battery systems is made or round to be inoperable for any reasons, continued reactor operation is permissible only during the succeeding three days pr)vided Specification 3 5.H is met unless such battery system !s sooner made operable.

c.

From and after the date that one of the two 24 volt ECCS Instrumentation battery systems is made or round to be 176 inoperable for any reason, continued l

reactor operation is permlasible only l

during the succeeding three days unless such battery system is sooner made operable.

Amendrient No. 58

c AVIILIARY ELECTRIC POWER SYSTEMS A.

The objectiva cf thia rpecification la to cssure that adequate power will be availtble to opertta the usergency safeguards equipment. Adequate power can be provided by any one of the following sources: either of the startup transformers, backfeed through the main transformer, the 4160 volt line from the Vernon Hydroelectric Station or either of the two diesel generators. The backfeed through the main transformer and 4160 volt Vernon line are both delayed-access offsite power sources. Backfeeding through the main transformer can be accomplished by disconnecting the main generator from the main transformer and energizing the auxiliary transformer from the 345 kv switchyard through the sain transformer. The time required to perform this disconnection is approximately six hours. The 4160 volt line from the Vernon Hydroelectric Station can be connected to either of the two emergency buses within seconds by simple manual switching operation in the main control room.

Two 480 V Uninterruptible Power Systems; each consisting of a battery bank, battery charger, and a sold state inverter, supply power to the LPCIS valves via designated motor montrol centers. The 480 V Uninterruptible Power

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Systems are redundant and independent of any onsite power sources.

This Specification assures that at least two offsite, two onsite power sources, and both 480 V Uninterruptible Power Systems will be available before the reactor is taken beyond "just critical" testing.

In addition to assuring power source availability, all of the associated switchgear must be operable as specified to assure that the emergency cooling equipment can be operated, if required, from the power sources.

Station service' power is supplied to the station through either the unit auxiliary transformer or the startup transformers.

In order to startup the station, at least one startup transformer is required to supply the station auxiliary load. After the unit is synchronized to the system, the unit auxiliary transformer carries the station auxiliary load, except for the station cooling tower loads which are always supplied by one of the startup transformers. The station cooling tower loads are not required to perform an engineered safety feature function in the event of an accident, therefore, an alternate source of power is not essential. Normally one startup transformer supplies 4160 volt buses 1 and 3 and the other supplies buses 2 and 4, however, the two startup transformers are designed with adequate capacity such that, should one become or be made inoper' Ole temporary connections can be made to supply the total station load (less the cooling towers) from the other startup transformer.

A battery charger is supplied for each battery. In addition the two 125 volt station batteries and the two 24 volt ECCS instrumentation batteries each have a spare chr.cger available. Since one spare 24 volt and one 125 volt charger are available, one battery charger can be allowed out of service for maintenance and repairs.

B.

Adequate power is available to operate the emergency safeguards equipment from either startup transformer or for minimum engineered safety features from either of the emergency diesel generators. Therfore, reactor operation is permitted for up to seven days with both delayed-access offsite power sources lost.

Each of the diesel generator units is capable of supplyir.g 100 percent of the minimum emergency loads required under postulated design basis accident conditions.

Each unit is physically and electrically independent of the other and of any offsite power source. Therefore, one diesel generator can be allowed out of service for a period of seven days without jeopardizing the safety of the station.

178 Amendment No. 58

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1 3 10 (cont'd) in the event that both startup transformers are lost, adequate power is availabir 90 operate the emergency safeguards equipment from either of the emergency diesel generators or from either of the de w ed-access offsite power sources.

Also, in the event that both emergency diesel Benerators are lost,' adequate power is available immediately to operate the emergency safeguards equipment from at least one of the startup transformers or from either of the delayed-access offiste power sources within six hours. The plant is designed to accept one hundred percent load rejection without adverse effects to the plant or the transmission system. Network stability analysis studies indicate that the loss of Vermont Yankee unit will not cause inability and consequent rippi a of the connecting 345 kv and 115 kv lines. The Vernon feed is an independent source. Thus, the availability of G.e delayed-access offsite power sources is assured in the event of a turbine trip. Therefore, reactor operation is permitted with the startup transformers out of service and with one diesel generator out of service provided the NRC is notifed immediatley of the event and restoration plans.

Either of the two station batteries has enough capacity to energize the vital buses and supply d-c power te the other emergency equipment for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> without being recharged. In addition, two 24 volt ECCS Instrumentation batteries supply power to instruments that provide automatic initiation of the ECCS and some reactor pressure and indication in

' the control room.

Due to the high reliability of probability of unwarranted shutdown by providing adequate time for reasonable repairs.

This minimuzes the probability of unwarranted shutdown by providing adequate time for reasonable repairs. A station battery, ECCS Instrumentation battery, or an Uninterruptible Power System battery is considered inoperable if more l

than one cell is out of service. A cell will be considered out of servica if its float voltage is below 2.13 volts and the specific gravity is below 1.190 at 770F.

The battery room is ventilated to prevent accumulation of hydrogen ga'.

With a complete loss of the ventilation s

system, the accumulation of hydrogen would not exceed 4 percent concentration in 16 days. Therefore, on loss of battery room ventilation, the use of purtable ventilation equipment acd daily sampling provide assurance that potentially hazardous quantities of hydrogen gas will not accumulate.

C.

The minimum diesel fuel supply of 25,000 gallons will supply one diesel generator for a minirma of seven days of operation satisfying the load requirements for the operation of the safeguards equipment. Additional fuel can be obtained and delivered to the site from nearby sources within the seven day period.

4.10 AUXILIARY ELECTRICAL POWER SYSTEMS Bases:

The test A.

The monthly tests of the diesel generators are conducted to check for equipment failures and deterioration.

of the undervoltage automatic starting circuits will prove that each diesel will receive a start signal if a loss of voltage should occur on its emergency bus. The loading of each diesel generator is conducted to demonstrate proper operation at less than the continuous rating and at equalibrium operating conditions. Generator experience at other generator stations indicates that the testing frequency 1.5 adequate to assure a high reliability of operattor, should the system be required.

173 Amendment No. 58