Text

Amend 12 to License NPF-13,correcting Administrative & Technical Deficiencies in Tech Specs Re low-low Set Function,Source Range Monitors & Div 2 Batteries
	ML20080T316
Person / Time
Site:	Grand Gulf
Issue date:	02/21/1984
From:	Schwencer A; Office of Nuclear Reactor Regulation
To:	;
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ML20080T319	List: ML20080T316;
References
	NUDOCS 8403010143
	Download: ML20080T316 (12)
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UNITED STATES

'o NUCLEAR REGULATOFlY COMMISSION E

WASHINGTON, D. C. 20555

%.....)7 MISSISSIPPI POWER AND LIGHT COMPANY MIDDLE SOUTH ENERGY, INC.

SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-*16 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE License No. NPF-13 Amendment No. 12 1.

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

A.

The applications for the amendment filed by the Mississippi Power and Light Company dated April 25, 1983, June 23, 1983, July 11, 1983,.and September 12, 1983, comply 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 applications, the provisions of the Act, 'and the regulations of the Comission; C.

There is reasonable assurance:

(i)thattheactivitiesauthorized 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.

'2.

Accordingly, the license'is amended as follows:

A.

Page changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) to read as follows:

(2) The Technical Specifications contained in Appendix A, as revised through Amendment No. 12, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensees shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8403010143 840221 PDR ADOCK 05000416 P

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. 3.

-.This-amendment is effective'as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ertataal signet >;s:

A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing Attachments:-

1.

Changes to the Technical Specifications Date of Issuance:

February 21

, 1984 7

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ATTACHMENT TO LICENSE AMENDMENT NO. 12 FACILITY OPERATING LICENSE NO. NPF-13 DOCKET NO. 50-416 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. These revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

REMOVE INSERT 3/4 3-10 3/4 3-10 3/4/3-14 3/4 3-14 3/4 3-23a 3/4 3-23a 3/4 3-39

-3/4-3-39 3/4 3-52 3/4 3-52 3/4 3-73 3/4 3-73 3/4 4-5 3/4 4-5 3/4 7-30 3/4 7-30 3/4 8-12 3/4 8-12 i

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TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION g

g VALVE GROUPS MINIMUM APPLICABLE q

OPERATED BY.

OPERABLE CHANNELS OPERATIONAL l

4 TRIP FUNCTION SIGNAL (a) PER TRIP SYSTEM (b)

CONDITION ACTION l.

h 1.

PRIMARY CONTAINMENT ISOLATION w

a.

Reactor Vessel Water Level-i Low Low,' Level 2 6A, 7, 8, 10(c)(d) 2 1, 2, 3 and #

20 I

b.

Reactor Vessel Water Level-Low Low Level 2 (ECCS -

Divisicn 3) 6B 4

1, 2, 3 and #

29

)

c.

Reactor Vessel Water Level-Low Low Low, Level 1 (ECCS -

Division 1 and Division 2) 5(")

2 1, 2, 3 and #

29 R.

d.

Drywell Pressure - High 6A, 7(c) M) 2 1,2,3 20

[

e.

Drywell Pressure-High (ECCS - Division 1 and e

S ")

2 1,2,3 29 I

o Division 2) f.

Drywell Pressure-High (ECCS - Division 3) 6B 4

1,2,3 29 g.

Containment and Drywell Ventilation Exhaust 2 *)

1, 2, 3 and

21 I

Radiation - High High 7

1 h.

Manual Initiation 6A, 7, 8, 10(c)(d) 2 1, 2, 3 and *#

22 h

2.

MAIN STEAM LINE ISOLATION l i a.

Reactor Vessel Water Level-

[

Low Low Low, Level 1 1

2 1,2,3 20 o

b.

Main Steam Line Radiation - High 1, 10(I) 2 1,2,3 23 c.

Main Steam Line e

Pressure - Low 1

2 1

24

~

d.

Main Steam Line f9) 1, 2, 3 23 5

Flow - High 1

2 e.

Condenser Vacuum - Low 1

2 1,

2,** 3**

P3

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e INSTRUMENTATION TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN ACTION 20 within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Close the affected system isolation valve (s) within one hour or:

ACTION 21 a.

In'0PERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 haurs.

b.

- In Operational Condition *, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary containment and x

. operations with a potential for draining the reactor vessel.

Restore the manual initiation function to OPERABLE status within ACTION 22 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Be in at least STARTUP with the associated isolation valves closed ACTION 23 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Bo in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas ACTION 25 treatment system operating within one hour.

ACTION 26' -

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system isolation valves within the next hour and declare the affected system inoperable.

~ ACTION 27 -'

Close the affected system isolation valves within one hour

- and declare the affected system inoperable.

i ACTION 28 '--

Lock the affected system isolation valves closed within one hour and declare the affected sy' stem inoperable.

Close the affected system isolation valves within one hour and ACTION 29 declare the affected systthe or component inoperable or:

a.

In OPERATIONAL CONDITION 1, 2 or 3 be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the i -

following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION # suspend CORE ALTERATIONS and opera-tions with a potential for draining the reactor vessel.

NOTES i

l Whenhandlingirradiatedfuelintheprimaryorsecondarycontainmentanddurind L.

CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The low condenser vacuum MSIV closure may be manually bypassed during reactor SHUTDOWN or for reactor STARTUP when condenser vacuum is below the trip setpoint to allow opening of the MSIVs. The manual bypass shall be removed when condenser vacuum exceeds the trip setpoint.

During CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

(a): See Specification 3.6.4, Table 3.6,a-1 for valves in each valve group.

(b) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped con-dition provided at least one other OPERA 8LE channel in the same trip system is monitoring that parameter.

(c) Also actuates the standby gas treatment system.

(d). Also actuates the control room emergency filtration system in the isolation mode of operation.

L (e) ' Two upscale-Hi Hi, one upscale-Hi Hi and one downscale, or two downscale signals from the same trip system actuate the trip system and initiate

. isolation of the associated containment and drywell isolation valves.

' GRAND GULF-UNIT 1 3/4 3-14 Amendment No. 7,8,9,12 g

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I TABLE 4.3.2.1-1 (Continued)

S ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS e

q; CHANNEL

. OPERATIONAL j.

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH z

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

[

6.

RHR SYSTEM ISOLATION (Continued) e.

Drywell Pressure - High S

M R

1,2,3 f.

Manual Initiation NA M(*)

NA 1,2,3 l

l

When handling irradiated fuel in the primary or secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

}

- The low condenser vacuum MSIV closure may be manually bypassed during reactor SHUTDOWN or for reactor STARTUP when condenser vacuum is below the" trip setpoint to allow opening of the MSIVs. The manual 4

bypass shall be removed when condenser vacuum exceeds the trip setpoint.

g

During CORE ALTERATION and operations with a potential for draining the reactor vessel.

(a) Manual initiation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days as part of circuitry required to be tested for automatic system isolation.

(b) Each train or logic channel shall he tested at least every other 31 days.

(c) Calibrate trip unit at least once per 31 days.

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c.

c INSTRUMENTATI'ON SURVEILLANCE REQUIREMENTS i

4.3.4.2.1' Each 'end-of-cycle recirculation pump trip system instrumentation

-channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.2.1-1.

4.3.4.2.2.-

LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all. channels shall be performed at least once per 18 months.

4.3.4.2.3 The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME of each trip function shown in Table 3.3.4.2-3 shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least the logic of one type of channel input, turbine control valve fast closure or turbine stop valve closure, such that both types of channel inputs are tested at least once per 36 months. The time allotted for breaker arc suppression,

.50 ms, shall be verified at least once per 60 months."

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" Prior to STARTUP after the first refueling outage, the breaker arc suppression time of 12 as, as determined by the manufacturer, shall apply.

i GRAND GULF-UNIT '

-3/4 3-39 Amendment No.

12

TABLE 3.3.6-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS cn TRIP FUNCTION TRIP SETPOINT ALLOWA8LE VALUE I'

1.

ROD PATTERN CONTROL SYSTEM E

a.

Low Power Setpoint 20 + 15, -0% of RATED THERMAL 20 +-15, -0% of RATED THERMAL POWER l

~

4 POWER b.

Intermediate Rod Withdrawal

< 70% of RATED THERMAL POWER

< 70% of RATED THERMAL POWER Limiter Setpoint-

~

2.

APRM a.

Flow Biased Neutron Flux-Upscale 1 0.66 W + 42%*

5 0.66 W + 45%*

b.

Inoperative NA NA d.

Neutron Flux - Upscale

-> 5% of RATED THERMAL POWER

-> 3% of RATED THERMAL POWER c.

Downscale

(

Startup 5 12% of RATED THERMAL POWER

$ 14% of RATED THERMAL POWER

,1 3.

SOURCE RANGE MONITORS J

Y a.

Detector not full in NA NA 5

5 b.

Upscale 5 1 x 10 cps 5 1.5 x 10 cp, c.

Inoperative NA NA d.

Downscale

> 0.7 cps

> 0.5 cps 4.

INTERMEDIATE RANGE MONITORS l

a.

Detector not full in NA NA l

b.

Upscale 5 108/125 of full scale 5 11C/125 of full scale c.

Inoperative NA NA d.

Downstale

> 5/125 of full scale

> 3/125 of full scale

{

5.

SCRAM DISCHARGE VOLUME l

E a.

Water Level-High 5 32 inches 5 33.5 inches 6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.

Upscale

$ 108% of rated flow

$ 111% of rated flow 2

w

The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow (W).

The trip setting of this function must be maintained in accordance with Specification 3.2.2.

1 I

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n INSTRUMENTATION SOURCE RANGE MONITORS l

LIMITING CONDITION FOR OPERATION 3.3.7.6 At least three source range monitor channels shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 2*, 3 and 4.

ACTION:

2.

In OPERATIONAL CONDITION 2* with one of the above required source range monitor channels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In OPERATIONAL CONDITION 3 or 4 with two or more of the above required source range monitor channels inoperable, verify all insertable con-trol rods to be fully inserted in the core and lock the reactor mode switch in the Shutdown position within one hour.

SURVEILLANCE REQUIREMENTS 4.3.7.6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:

a.

Performance of a:

1.

CHANNEL CHECK at least'once per:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in CONDITION 2*, and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in CONDITION 3 or 4.

2.

CHANNEL CALIBRATION ** at least once per 18 months.

b.

Perform &nce of a CHANNEL FUNCTIONAL TEST:

1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to moving the reactor mode switch from the Shutdown position, if not performed within the previous 7 days, and a

2.

At least once per 31 days.

c.

Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.7 cps with the detector fully inserted.

With IRM's on range 2 or below.

- Neutron detectors may be excluded from CHANNE,L CALIBRATION.

GRAND GULF-UNIT 1 3/4 3-73 Amendment No.

12

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REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2.1 Of the following safety / relief valves, the safety valve function of at least 7 valves and the relief valve function of at least 6 valves other than those satisfying the safety valve function requirement shall be OPERABLE with the specified lift settings:

Number of Valves Function Setpoint* (psig) 8 Safety 1165 1 11.6 psi 6

Safety 1180 1 11.8 psi 6

Safety 1190 1 11.9 psi 1

Relief 1103 1 15 psi 10, Relief 1113 1 15 psi l

9 Relief 1123 1 15 psi APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a.

With the safety and/or relief valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 105*F, close the stuck open relief valve (s); if unable to close the open valve (s) within 2 minutes or if suppression pool average water temperature is 105*F or greater, place the reactor mode switch in the Shutdown position.

c.

With one or more safety / relief tail pipe pressure switches inoperable, restore the inoperable switch (es) to OPERABLE status within 7 days or be l

in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.2.1.1 The tail pipe pressure switch for each safety / relief valve shall be demonstrated OPERABLE with the setpoint verified td be 30 5 psig by performance of a:

r a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and a b.

CHANNEL CALIBRATION at least once per 18 months.**

4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a.

CHANNEL FUNCTIONAL TEST, including calibration of the trip unit, at least once per 31 days.

b.

CHANNEL CALIERATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic operation of the entire system at least once per 18 months.

The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the test.

g Initial opening of 1821-F051B is 1103 1 15 psig due to low-low set function.

GRAND GULF-UNIT 1 3/4 4-5 Amendment No. 9, 12

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A

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-75, is within the acceptable limits specified in Table 1 of ASTM 0975-77 when checked for viscosity, water and sediment.

c.

'At least once per 18 months during shut'down, by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

4.7.6.1.3 The diesel driven fire pump starting 24-volt battery bank and charger shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that:

1.

The electrolyte level of each cell in each battery is above the plates, and 2.

The overall battery set voltage is greater than or equal to 24 volts.

b.

At least once per 92 days by verifying that the specific gravity for each cell is appropriate for continued service of the battery. The specific gravity, corrected to 77*F and full electrolyte level, shall be is greater than or equal to 1.20.

At-least once per 18 months Adr verifying that:

c.

1.

The battery case and battery racks show no visual indication of physical damage or abnormal deterioration, and 2.

Battery terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

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l GRAND GULF-UNIT 1 3/4 7-30 Amendment No.

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. ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

At least once per 18 months, during shutdown, by verifying that either:

1.

The battery capacity is adequate to supply and maintain in OPERA 8LE status all of the actual emergency loads for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Divi-sions 1 and 2 and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Division 3 when the battery is subjected to a battery service test, or 2.

The battery capacity is adequate to supply a dummy load of the following profile, which is verified to be greater than the actual emergency load, while maintaining the battery terminal voltage greater than or equal to 105 volts.

a)

Division 1 1950 amperes for the first 60 seconds 1128 amperes for'the next 119 minutes 1306 amperes for the next 60 seconds 1128 amperes for the next 118 minutes 1416 amperes for the last 60 seconds b)

Division 2 1427 amperes for the first 60 seconds 2186 amperes for the next 119 minutes 3357 amperes for the eext 60 seconds 2186. amperes for the next 118 minutes 1243 amperes for.the last 60 seconds c)

Division 3 176 amperes for the first 60 seconds 116 amperes for the next 59 minutes 118 amperes for the last 60 minutes s.

s At least once per 60 months during shutdown by verifying that the e.

battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Once per 60 month interval, this performance discharge test may be performed in lieu of the battery service test.

f.

Annual performance discharge tests of battery capacity shall be given-to any battery that shows signs of degradation or has reached 85% of the service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.

GRAND GULF-UNIT 1 3/4 8-12 Amendment No.

12

- ~ ~ -

___

ML20080T316

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