Text

Amend 2 to License NPF-9,correcting Typographical Errors & Revising RCS Testing Requirements
	ML19343D035
Person / Time
Site:	McGuire
Issue date:	04/02/1981
From:	Youngblood B; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19343D036	List: ML19343D035; ML19343D038; ML19343D039;
References
	TAC-46812, NUDOCS 8104090128
	Download: ML19343D035 (18)
	v • d • e

.

.# "% 7o,,

S UNITED STATES E U UIt UllIUl31 L

NUCLEAR REGULATORY COMMISSION

%_.[*'7

,' @, / j v AssiNcTON, D. C. 20555 a mw,i ;

e 8.. *****

DUKE POWER COMPANY DOCKET !0. 50-369 MCG1JIRE NUCLEAR STATION, UNIT 1 LICENSE FOR FUEL LOADING AND ZERO POWER TESTING License No. NPF-9 Arendnent No. 2 1.

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

A.

The issuance of this ar.encrent to the Dui.e Power Cc pany for tne "cGuire Nuclear Staticn, Unit 1 con? lies with t*.e standards and requirements of the Atonic Energy Act of 1954, as a ended (the Act) and the Commission's rules and regulations set fertn in 10 CFR Chapter I; E.

The facility will operate in conformity sith the license, as a. ended, the orovisions of the Act anc the rules anc regulations cf tne Ccri s sicn; C.

Tiiere is reasonable assurance (i) that the activities authcri:ed by this arend~ent can be conducted without endangering tre heslth and safety of the rublic, and (ii) that such activities wiil be ccnf.ucted in compliarce with the Commissicn's regulations; D.

The issuance of tnis amendnent will not be inimical to the comon defense and security or to tne health and safety cf the public; and E.

The issuance of this amendment is in accordance with 10 CFR ? art 51 of the Ccc-ission's regulations and all applicable requirements have been sa.isfiec.

C104090 @

. gg ORGM.

2.

Accorcir. gly, the license is amended by chang ne Appendix A Tecnnical Specifications as indicated in the attachment to this license arend ent. License !;PF-9 for Fuel Leading and Zero Power Testing is nerey amenced to read as follows:

(2) Technical Specifications The Tecnnical Specifications contained in. Appencix A as revised tq-cug. Amendment 'Jo. 2, are hereby incorporated into this license.

T: licensee shall coerate the facility in accordance with the Techrical Specificaticas.

2.

tis license a enc ent is effective as of the date of issuance.

FCR THE !;UCLEAs REGULATORY CC!CISSION

/,

'i j

j

~.w.

/

B. J. icungblocc, Chief Licensing Brar.cn i;o.1 Divisicn of Licensing Ca:e of :ssuar.ce:

APR 2 1331 E :1csure:

.'se: : ges :: A:pendix A

-e:r-ica' Sp=:ifications

ATTACHMENT TO LICENSE AMENDMENT NO. 2-LICENSE FOR FUEL LOADING AND ZERO POWER TESTING,- f:PF-9 DOCKET NO. 50-369 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Pages 3/4 4-18.

3/4 4-19 3/4 4-20 3/4 5-1 3/4 7-60 3/4 8-9 3/4 6-1 2-7 2-9 3/4 1-7 3/4 1-8 3/4 3-50 l

3/4 3-51 i

3/4 4-8 l

3/4 4-9 l

l l

r

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITIbGCONDITIONFOROPERATION 3.4.7.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKACE, b.

1 GPM UNIDENTIFIED LEAKAGE, c.

1 GPM total primary-to-seconiary leakage through all steam generators and 500 gallons per day through any one steam generator.

d.

10 GPM IDENTIFIED LEAKAGE fro 1 the Reactor Coolant System, e.

40 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 20 psig, and f.

1 GPM leakage at a Reactor Coolant System pressure of 2235 1 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00kN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE B(.U.'lDARY LEAKAGE and leakage from Reactor Pressure I:;olation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at laast HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

McGUIRE - UNIT 1 3/4 4-18 Amendment No. 2 3

~

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

Monitoring the containment atmosphere gaseous radioactivity monitor a.

at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

Monitoring the contairment sump inventory and discharge at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i c.

Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals when the Reactor Coolant System pressure is 2235 20 psig at least once per 31 days.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

e.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.7.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 18 months.

b.

Prior to entering MODE 2 whenever the plant has been in COLD SHUTOOWN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has not been performed in the previous 9 months.

c.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve.

d.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valva.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

McGUIRE - UNIT 1 3/4 4-19 Amendment No. 2

TA8LE 3.4-1 REACTOP. COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER FUNCTION MC-1562-2.0 INI60 Accumulator Discharge 1NI71 Accumulator Discharge-1NI59 Accumulator Discharge 1NI70 Accumulator Discharge MC-1562-2.1 1NI182 Accumulator Discharge INI94 Accumulator Discharge INI81 Accumulator Discharge 1NI93 Accumulator Discharge MC-1562-3.0 INI159 Safety Injection (Hot Leg)

INI156 Safety Injection (Hot Leg)

INI128 Safety Injection (Hot Leg)

INI124 Safety Injection (Hot Leg) 1NI160 Safety Injection (Hot Leg) 1NI157 Safety Injection (Hot Leg) 1NI126 SafetyrInjection (Hot Leg)

MC-1562-3.1 INI165 Safety Injection / Residual Heat Removal (Cold Leg) 1NI167 Safety Injection / Residual Heat Removal (Cold Leg)

IN1169 Safety Injection / Residual Heat Removal (Cold Leg)

INI171 Safety Injection / Residual Heat Removal (Cold Leg) 1NI175 Safety Injection / Residual Heat Removal (Cold Leg) 1NI176 Safety Injection / Residual Heat Removal (Cold Leg) 1NI180 Safety Injection / Residual Heat Removal (Cold Leg) 1NI181 Safety Injection / Residual Heat Removal (Cold Leg) l1C-1562-4.0 1NI250 Upper Head Injection 1NI251 Upper Head Injection INI252 Upper Head Injection j

1NI253 Upper Head Injection 1NI249 Upper Head Injection l

1NI248 Upper Head Injection MC-1561-1.0 1

1 INDIB*

Residual Heat Removal i

IND2A*

Residual Heat Removal

.1

^ Testing per Section 4.4.7.2.2.d not applicable due to positive indication of valve position in Control Room.

1 McGUIRE - UNIT 1 3/4 4-20 Amendment No. 2 d'

3/4.5-EMERGENCY CORE COOLING SYSTEMS

- 3/4.5.1 ACCUMULATORS-COLD LEG INJECTION ACCUMULATORS LIMITING CONDITION FOR OPERATION

-3.5.1.1_ Each cold leg injection accumulator shall be OPERABLE with:

a.

The isolation valve open, 4

b.

A' contained borated water volume of between 8261 and 8496 gallons, c.

.Between 1900 and 2100 ppm of boron, and d.

'A nitrogen cover pressure of-between 400 and 454 psig.

APPLICABILITY:

MODES l'.2 and 3.*

ACTION:

4 a.

With one cold leg injection accumulator inoperable, except as a result of a closed isolatio.n valve,. restore the inoperable ~ cold leg injection accumulator to OPERASLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTOOWN within the following,6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one cold leg injection accumulator inoperable due to the isolation valve being closed, either immediately open the isolation l

valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.1.l.1 Each cold leg injection accumulator shall be demonstrated OPERABLE:

i-a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1.

Verifying, by the absence of alarms, the contained borated j

water volume and nitrogen cover pressure-in the tanks, and-2.

Verifying that each cold leg injection accumulator isolation valve is open.

u

^ Pressurizer pressure above 1000 psig.

i:

McGUIRE -_ UNIT _1 3/4 5 Amendment No. 2 i

A

TABLE 3.7-6 FIRE HOSE STATIONS LOCATION ELEVATION 55-FF 695 ft.

=

52-CC 716 ft.

54-GG 716 ft.

55-MM 716 ft.

51-MM 716-ft.

40-AA 733 ft.

40-CC 733 ft.

43-D0 733 ft.

46-AA 733 ft.

l 52-DD 7' 3 f t.

52-EE 733 ft.

54-GG 733 ft.

51-JJ 733 ft.

52-MM 733 ft.

55-NN 733 ft.

46-CC 750 ft.

51-CC 750 ft.

52-AA 750 ft.

54-8B 750 ft.

~

55-00 750 ft.

58-BB 750 ft.

52-GG 750 ft.

54-LL 750 ft.

50-MM 750 ft.

56-QQ 750 ft.

51-BB 767 ft.

56-GG 767 ft.

54-JJ 767 ft.

51-MM 767 ft.

McGUIRE - UNIT 1 3/4 7-60 Amendment No. 2

=.

ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall bo OPERABLE:

a.

One circuit between the offsite transmission network and the onsite essential auxiliary power system, and b.

One diesel generator with:

i 1.

A day tank containing a minimum volume of 120 gallons of fuel, 2.

A fuel storage system-containing a minimum volume of 28,000 gallons fo fuel, and 3.

A fuel. transfer pump.

APPLICABILITY: MODES'S and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources-OPERABLE, suspend all cperations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 -

4.8.1.1.2 and 4.8.1.1.4 except for Requirement 4.8.1.1.2.a.5.

d 1

McGUIRE - UNIT 1 3/4 8-9 Amendment No. 2

,,v-

=,

3/4.6 CONTAINMENT SYSTEMS 3/4.6.l PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMIT;NG CONDITION FOR OPERATION 3.6.1.1 -Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2,'3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a.

At lost once per 31 days by verifying that all penetrations

not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in lable 3.6-2 of Specification 3.6.3.

b.

By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

c.

Af ter each closing of a penetratiori subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at Pthat when the measured leakage r 14 ls is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L *a

Except valves, blind flanges, and deactivated automatic valves which are

' cated inside the annulus or containment and are locked, sealed or otherwise secured in the closed position.

These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

i McGUIRE - UNIT 1 3/4 6-1 Amendment No. 2

TABLE 2.2-1 (Continued)

?'8 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT-ALLOWABLE VALUES

^

E 20.

Power-Range Neutron Flux -

5 48% of RATED THERMAL POWER

$ 49% of RATED THERMAL POWER q

(P-8) Low Reactor Coolant

_g Loop Flow, and Reactor Coolant Pump Breaker Position 21.

Power Range Neutron Flux -

> 10% of RATED THERMAL POWER

> 9% of RATED THERMAL POWER (P-10) - Enable block of Source, Intermediate, and Power Range (low setpoint)

Reactor Trips 22.

Reactor Trip P-4 Not Applicable Not Applicable NOTATION T

f s

I+ IS 140TE 1:

Overtemperature AT5 AT, [K -K2 (T-T')+K (P-P')-f (AI)]

j 3

j l+'2 f S

s where: AT, Indicated AT at RATED THERMAL POWER

=

Average temperature, *F T-

=

T' 5 588.2*F Reference T at RATED THERMAL POWER avg N

Pressurizer pressure, psig g

P

=

@g P'

2235 psig (Nominal RCS operating pressure)

=

e I*I b = The function generated by the lead-lag controller for T dynamic compensation

.E l

avg r) & T2= Time constants utilized in the lead-lag controller for T,yg t) = 33 secs, 2 = 4 secs.

1

~1 S

Laplace transform operator, sec

=

TABLE 2.2-1 (Continued)

N REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E

NOTATION.(Continued) m E

'Tb 3

Note 2:

Overpower AT $ AT [K -K T-K6 (T-T")-f (OI)3 g 4 5

.1+1 S 2

3-where:

AT, Indicated AT at RATED THERMAL POWER

=

Average temperature, *F T

=

T"

$ 588.2 F Reference T,yg at RATED THERMAL POWER

=

1.0908 K4 0.02/*F for increasing average temperature and 0 for decreasing average K

=

5 temperature K

0.00126/ F for T > T"; K6 = 0 for T $ T"

=

6

'3b The function generated by the rate lag controller for.T

=

avg 1+T 5 dynamic compensation 3

Time constant utilized in the rate lag controller for T r

=

3 avg 3 = 5 secs.

T Laplace transform operator, sec'1 f

S

=

k f (AI) =

0 for all AI 2

2 Note 3:

The channel's maximum trip point shall not exceed its computed trip point by more than

.o 2 percent.

m

REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATH - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following baron injection flow paths shall be OPERABLE:

a.

A flow path from the boric acid tanks via a boric acid transfer pump and charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.5a is OPERABLE, or b.

The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.5a is OPERABLE.

APPLICABILITY: MODES 5 and 6.

ACTION:

With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

=

SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that the temperature of the heated portion of the flow path is greater than or equal to 65 F when a flow path from the boric acid tanks is used.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

McGUIRE - UNIT 1 3/4 1-7 Amendment No. 2

REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITblGCONDITIONFOROPERATION 3.1.2.2 At least two of the following three boron injection flow paths shall be OPERABLE:

a.

The flow path from the boric acid tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System, and b.

Two flow paths from the refueling water storage tank via a charging pump to the Reactor Coolant System.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1%

delta k/k at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two flow paths to GPERABLE status within the next 7 days or be in COLD SilVT00WN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that the temperature of the heated portion of the flow path from the boric acid tanks is greater than or equal to A5 F when it is a required water source.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c.

At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection (S ) test signal.

s d.

At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2.a delivers at least 30 gpm to the Reactor Coolant System.

nly one baron injection flow path is required to be OPERABLE whenever the 0

temperature of one or more of the RCS cold legs is less than or equal to 300 F.

McGUIRE - UNIT 1 3/4 1-8 Amendment No. 2 A

w m-TABLE 3.3-10

?jj ACCIDENT MONITORING INSTRUMENTATION M

REQUIRED NO.

MINIMUM EE OF CHANNELS Ci INSTRUMENT CHANNELS OPERABLE a

1.

Containment Pressure 2

1 2.

Reactor Coolant lemperature - T and TCOLD (Wide Range) 2 1

H0T 3.

Reactor Coolant Pressure - Wide Range 2

1 4.

Pressurizer Water Level 2

1 S.

Steam Line Pressure 2/ steam generator 1/ steam generator 40 6.

Steam Generator _ Water Level - Narrow Range 2/ steam generator 1/ steam generator u

f 7.

Refueling Water Storage Tank Water Level 2

1 8.

Auxiliary feedwater Flow Rate 2/ steam generator 1/ steam generator 9.

Reactor Coolant System Subcooling Margin Monitor 1

0 10.

PORV Position Indicator 2/ valve 1/ valve 11.

PORV Block Valve Position Indicator 1/ valve 1/ valve 12.

Safety Valve Position Indicator 2/ valve 1/ valve 13.

In-Core Thermocouples 4/ core quadrant 2/ core quadrant 2,n 14.

Containment Water Level 2

1 R

Me

.O

w TABLE 4.3-7 5

ACCIDENT MONITORING INSTRilMENTATION SURVEILLANCE REQUIREMENTS E

m CHANNEL CHANNEL E

INSTRUMENT CilECK CALIBRATION Z

~

1.

Containment Pressure M

R COLD (Wide R'ange) 2.

Reactor Coolant Temperature - T and T M

R 110T 3.

Reactor Coolant Pressure - Wide Range M

R 4.

Pressurizer Water Level M

R 5.

Steam Line Pressure M

R g

6.

Steam Generator Water Level - Narrow Range M

R 4

Y 7.

RWST Water Level M

R w

8.

Auxiliary Feedwater Flow. Rate M

R 9.

Reactor Coolant System Subcooling Margin Monitor M

-R 10.

PORV Position Indicator M

R 11.

PORV Block Valve Position Indicator M

R 12.

Safety Valve Position Indicator M

R-Eg 13.

In-Core Thermocouples M

R

%g 14.

Containment Water Level (Wide Range)

M R

re e

.A.

REACTOR COOLANT SYSTEM 3/4.4.4 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with a water volume of less than or equal to 1600 cubic feet (equivalent to an indicated level of less than or equal to 92% on narrow range instrument), and at least two groups of pressorizer j

heaters each having a capacity of at least 150 kw.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

a.

With one group of pressurizer heaters inoperable, restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the follow-ing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

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

e

't SURVEILLANCE REQUIREMENTS 4.4.4.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.4.2 The capacity of each of the above required groups of pressurizer heaters shall be verified at least once per 92 days.

4.4.4.3 The emergency power supply for the pressurizer heater shall be deconstrated OPERABLE at least once per 18 months by manually transferring power from the normal to the emergency power supply and energizing the heaters.

McGUIRE - UNIT 1 3/4 4-8 Amendment No. 2 J

2

REACTOR COOLANT SYSTEM 3/4.4.5 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.5 All power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve (s) to OPERABLE status or close the block-valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.3.2.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a.

Performance of a CHANNEL CALIBRATION, and b.

Operating the valve through one complete cycle of full travel.

4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

4.4.3.2.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by:

a.

Manually transferring motive and control power from the normal to the emergency power supply, and b.

Operating the valves through a complete cycle of full travel.

McGUIRE - UNIT 1 3/4 4-9 Amendment No. 2

.

v t e Letter Sequence Other
TAC:46812, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request Acceptance... Administration Questions Answers Results Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval Other: ML19341A422, ML19341A424, ML19341B423, ML19341C004, ML19341C007, ML19343B857, ML19343D035, ML19343D039, ML19351A069, ML19351G105, ML20003A648, ML20003A650, ML20003A653, ML20005A189, ML20008E635, ML20010B899, ML20010H761, ML20010H997, ML20030D756, ML20031B542, ML20031D162, ML20031D166, ML20031D172, ML20031D176, ML20031D178, ML20032B192, ML20032B195
MONTHYEAR1981-06-12 [Table View]

ML19343D035

Text

Navigation menu

Search