Text

Amend 8 to License NPF-5,revising Certain Action Statements Applicable to Reactor Protection Sys & Isolation Actuation Instrumentation
	ML19241C132
Person / Time
Site:	Hatch
Issue date:	07/03/1979
From:	Ippolito T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19241C133	List: ML19241C132; ML19241C134; ML19241C135;
References
	NUDOCS 7907270322
	Download: ML19241C132 (17)
	v • d • e

'gvMcg%

UNITED STATES j

g 3 'e

.* t NUCLEAR REGULATORY COMMISSION h

)

W ASHINGTON. D. C. 20555 WQ/e/

g

+.....

GEORGIA POWER COMPANY

~

OGLETHORPE ELECTRIC MEMBERSHIP CORPORATION MUNICIPAL ELECTRIC ASSOCIATION OF GEORGIA CITY OF DALTON, GEORGIA 00_CKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No. NPF-5 1.

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

A.

The application for amend ent by Georgia Power Company, et al,, (the licensee) dated May 22, 1979, c ompl i es with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comnission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by tnis amendrent cai, be conducted without endannering the health and safety of the public, and (ii) that such activities will be conducted in conpliance with the Conmission's regulations; D.

The issuance of this amendment will not be inimical to the connon 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 requirenents hwe been satisfied.

f0 Ik N b t

7 907 270 '36;R;?2.

. 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. NPF-5 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained ~n Appendices A and B, as revised through Amendment No. 8, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

F0k THE NUCLEAR REGULATORY COMMISSION VCG <fyfse- {'$ z>

^-

Thomas A/Ippolito, Chief Operating Reactors Branch =3 Division of Operating Peactors Attache

'1 Changes to the Technical Specifications Date of Issuance: July 3, 1979 I b Il 2 kl[

ATTAfHMFNT To iICENSE_f(1ENDME!!T NO._3 FACIL ITY OPERAT ING LICENSE NO. NPF-5 DOCKET NO. 50-366 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.

Renove Insert 3/4 0-1 3/4 0-1 3/4 0-2*

3/4 0-2*

3/4 3-1 3/4 3-1 3/4 3-2*

3/4 3-2*

3/4 3-3*

3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-6*

3/4 3-6*

3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10 3/4 3 '. 5 3/4 3-15 3/4 3-16*

3/4 3-16*

B 3/4 0-1 B 3/4 0-1 B 3/4 0-2*

B 3/4 0-2*

?

0verleaf provided for convenience only.

Es b 5 E' k

l!3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL CONDITIONS or other states specified for each specification.

3.0.2 Adherence to the requirements of the Limiting Condition for Operation and associated ACTION within the specified time interval shall constitute compliance with the specification.

In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

3.0.3 In the event a Limiting Condition for Operation and/or associated ACTION reouirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the facility shall be placed in at least HOT SHUT OWN within 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 un' s corrective measures are completed that permit operation under the per-issible ACTION statements for "e specified time interval as reasured from initial discovery or until'the reactor is placed in an OPERATIONAL CONDITICN in which the specification is not applicable.

Exceptions to these requirements shall be stated in the individual specifications.

3.0.4 Entry into an 0;'ERATIONAL CONDITION or other specified applicability state shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION state-ents unless other. vise excepted.

This provision shall not prevent nassage thru OPERATIONAL CONDITIONS required to comply with ACTION requirements.

SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirenents shall be applicable during the OPERA-TIONAL CONDITIONS or other states specified for individual Limiting Conditions for Operation unless otherwise stated in the individual Surveillance Requirements.

a.0.2 Each Surveillance Requirement shall be performed within the specified tine interval with:

A maximum allowable extension not to exceed 251 of yJ u 2,4h a.

5 surveillance interval, I HATCH - UNIT 2 3/4 0-1 Anendment No. B

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) b.

A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPEPABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

Surveillance require-ments do not have to be perfomed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable state shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall bc applicable as follows:

a.

During the time p riod:

r 1.

From issuance of the Facility Operating License to the start of facility commercial operation, inservice testing of ASME Code Class 1, 2, & 3 pur js and valves shall be performed in accordance with Section XI of the ASME Boiler and Dressure Vessel Code 1974 Edition, and Addenda through sumer 1975, except where specific written relief has been granted by the Comission.

2.

Following start of facility comercial operation, inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be perforied 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 Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

"ATCH - UNIT 2 3/4 0-2 2v7 f4 M

TABLE 3.3.1 -1 REACTOR PROTECTION SYSTEM ItiSTRUMEtiTATION h

APPLICABLE MINIMUM NUMBER OPERATIONAL OPERABLE CHANNELS p

7 FUNCTIONAL UNIT CONDITIO L PER TRIP SYSTEM (a)

ACTION 1.

Intennediate Range Mdnitors:

(2C51 -K601 A, B, C, D, E, F, G, H) a 2(c),5(b) 3 1

a.

Neutron Flux - High 3, 4 2

2 0')

b.

".noperative 2, 5 3

1 3, 4 2

2 2.

Average Power Range Monitor:

(2C51-K605 A, B, C, D, E, F) a.

fleutron Flux - High,15%

2, 5 2

1 b.

Flow Biased Neutron Flux -

High 1

2 3

c.

Inoperative 1, 2, 5 2

4 d.

Downscale 1

2 3

e.

LPRM 1, 2, 5 (d)

NA

[

3.

Reactor Vessel Steam Dome Pressure -

High (2B21-N023 A, B, C, D) 1,2(e) 2(j, 2B21 -N045-5 A,B,C,D) 4.

Reactor Vessel Water Level -

2(j* 2B21-N024-5 Low (2B21-N017 A, B, C, D) 1, 2 A, B and 2B21 -N025-

%g A,B) 5.

Main Steam Line Isolation Valve 1(7) 4 3

Closure (NA) 6.

Main Steam Line Radiation - High 1, 2 ")

2 6

b (2Dll-K603 A, B, C, D) 7.

Drywell Pressure - High 1, 2 2

5

( N, N (2C71-N002 A, B, C, D)

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation :hannels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

Set points and interlocks are given in Table 2.2.1-1.

APPL ICABIL ITY_:

As shown in Table 3.3.1-1.

ACTION:

a.

With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place at least one inoperable channel in the tripped condition within one hour, b.

With the requirrents for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one inoperable channel in at leatt one trip system

in the tripped condition within one hour ano take tle ACTION required by Table 3.3.1-1.

c.

The provisions of Specification 3.0.3 are not applicable in OPERA-TIONAL CONDITION 5.

SURVEILLANCE REOUIREMENTS 4.3.1.1 Each reactor protection system instrunentation channel snall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTION TEST and CHANNEL CALIBRATION operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operaticn of all channels shall be performed at least once per 18 months End shall include calibration of tine delay relays and timers necessary for proper functioning of the trip system.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at

! east once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 nonths and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function.

1f both channels are inoperable in one trip system, select at least one increrable channel in that trip system to place in the tripped conditions, except when this could cause the Trip Function to occur.

HATCH - UNIT 2 3/4 3-1 Amendment No. 8 gg kNb N

W

[

TABLE 3.3.1-1 (Continued) 9 PEACTOR PROTECTION SYSTEM INSTRUMENTATION APPLICABLE MINIMUM NUMBER

-d OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM M ACTION N

8.

Scram Discharge Volume Water Level - High (2Cll-N013 A, B, C, D) 1,2,5(h) 2 4

I}

4('}

7 9.

Turbine Stop Valve - Closure (NA) 1 10.

Turbine Control Valve Fast Closure, 1(i) 2(k) 7 Trip Oil Pressure - Low (2C71-N005 A, B, C, D)

R 11.

Reactor Mode Switch in Shutdown Position (NA) 1,2,3,4,5 1

8 3-12.

Manual Scram (NA) 1,2,3,4,5 1

9 NN h

a

'If

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 In OPEPATIONAL CONDITION 2, be in at least HDT SHUTDOWN l

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In OPEPATIONAL CONDITION 5, suspend all operations ir.volving CORE ALTERATIONS or postive reactivity changes and fully insert all insertable control rods within one hour.

ACTION 2 - Lock the reactor mode switch in the Shutdown position within one hour.

l ACTION 3 - Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 4 -

In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN j

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , In OPEPATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

ACTION 5 - Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l Be in ETARTUP with the main steam line isolation valves closed ACTION 6 -

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or in at least HDT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

{

Initiate a redu. tion in THERMAL POWER within 15 minutes and ACTION 7 be at less then 30% of RA~ED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN ACTION 8 l

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In OPERATIONAL CONDITION 3 or 4, immediately and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months verify that all.ontrol rods are fully inserted.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

HATCH - UNIT 2 3/4 3-4 A endrent No.

8 2p

?bV h

TABLE 3.3.1-1 (Continued)

RrACTOR PROTECTION SiSTEM INSTRUMENTATION ACTION 9 -

In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN l

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In OPERATIONAL CONDITION 3 or 4, lock the reacter mode switch in the Shutdown position within one hour.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

TABLE NOTATIONS 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 a.

required surveillar.ce without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

b.

The " shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accordance with Specification 3.10.3.

The IRM scrams are autom.atically byp'assed when the reactor vessel mode c.

s.titch is in the Run position and all ;PRM channels are OPERABLE and on scale.

d.

An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than uleven LPRM inputs to an APRM ciu nnel.

e.

These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.

f.

This function is automatically bypassed when the recctor mode swittn is in other than the Run position.

This function is not required to be OPERABLE when PRIMARY CONTAINMENT g.

INTEGRITY is not required, h.

With any control rod withdrawn.

Not applicable to control rods removed per Speci fi cation 3.9.11.1 or 3.9.11.2.

i.

These functions are bypassed when turbine first stage pressure is

<2:n* psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.

j.

Also trips reactor coolant system recirculatici pump MG sets.

k Also trips reactor coolant system retirc Tction pump motcrs.

Final setpoint to be determined during startup [8 Ib

Ini tial setpoint.

tes ing.

sg g sATCn - umT 2 3/4 3-s unendment No.

TABLE 3.3.1-2 m,,

RE ACTOR PPOTECTI_O_N SYSTEM RE_S_P_0'6_ _E TIME _S b

FUNCTIONAL UNIT RESPONSE TIME d econEsT-c_

5

-i 1.

nterrediate Range Monitors:

"3 a.

Neutron Flux - High*

NA b.

Inoperative NA 2.

Average Poner Range Monitor

a.

Nrot < < n Fl ux - High,15%

1 0.09 b.

FI'm dia,ed Neutron Flux High 0.09 c.

Inoperative NA d.

Downscale NA e.

LPRM NA 3.

Reactor Vessel Steam Dome Pressure - High 1 0.55 4.

Reactor Vessel Water Level - Low 1 1.05 5.

Main Steam Line Isolation Valve -Closure 1 0.06

[

6.

Main Steam Line Radiation - High NA 7.

Dryweil Pressure - High NA 8.

Scrao Discharge Volume Water Level - High NA 9.

Turbine Stop ','alve - Closure 1 0.06 10.

Turbine Control Valve Fast Closure, Trip Oil Pressure - Low

_ 0.08 11.

Reactor Mo6a Switch in Shutdown Position NA 12.

Manual Scram NA h

4heutron detectors are exempt from response time testing.

Response time shall be measured from detector output or input of first electronic component in channel.

UmW

INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY:

As shown in Table 3.3.2-1.

ACTION:

a.

With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable and place the inoperable channel in the tripped condition

until the channel is restnred tc OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b, With the requirerents for t.e minimun number of GPERABLE channels not satisfied for one trip system, place at least one inoperable channel in the tripped condition

within one hour.

c.

With the require enis for the mininu nurner of CDERABLE channels not satisfied '~c1 both trip systens, place at least one inoper-able channel in at least one trip syste-** in the trippec condition within one hour and take the ACTICN required by Table 3.3.2-1.

d.

The provisionc of Specification 3.0.3 are not applicable in OPERATIONAL CCNNTION 5.

SURVEILLANCE REQUIREMENTS a.3.2.1 Each isolation actuaticn instrumentation chan-ci shall be demonstrated OPERAELE b;. the performance of the CHANN' K, CHANNEL FUNCTIONAL TEST AND CHA',NEL CALIBRATION operations durin 2 OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2-1.

Litr a cesicn provicina enly one channel per trip system, an inocerable channel need not be placed in the tripped condition where this vould caust tac.rlo Functicq to occur.

In these cases, the inoperable charr 1 shall be re *~ e-to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the art:

rew i re ' b,

'e

' 7.2-1 for that Trip Function shall t'n tM en.

s m "able in one trip 5:, sten, select at ist ene innerable channci in that trip syste" to pia n in the tri'.M j

conj' tien, excert when that would cause the Trip ranctinn to occur.

HATCH - UNIT 2 3/4 3-9 Arencrent No.4 D g

')-; hf

INSTRUMENTATION SURVEILLANCE RE0VIREMENTS (Continued)

?.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic cperation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least once por lE months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested 3t least once every N tire: 18 months, where N is the total numbe: of redundant channels in a specific isolation function.

lh-

%TCH - UNIT 2 3/4 3-10 a

f a.

TAFLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 -

Se in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SH'JTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Be in at least STARTUP with the main steam line isolation valves ACTION 21 closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT CHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I ACTION 22 -

Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 -

Be in at least STARTUP with the Group 1 isolation valves closed within 2,urs or in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l Establish SECONDARY CONTAINMENT INTEGPITY with the standby ACTION 24 -

nas treatrent system operating within one hour.

ACTION 25 -

Isolate the reactor water cleanup system.

ACTION 26 -

Close the affected system isolation valves and declare the affected system inoperable.

ACTION 27 Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or close the affected system isolation valves and declare the affected syster inoperable.

ACTID' 28 -

Close the shutdcwn cooling supply and reactor vessel head spray isolation valves unless reactor steam done pressure 1 135 psig.

NOTES Actuates oceration ci tne main control room environrental control syster in the pres urication node of operation.

Actuates the standby gas treatment syste.

When handling irradiated fuel in the secondary containment.

er Speci ficat' >n 3.6. ' 1, Table 3.6.3.1-1 for valves in each valve groun.

c a.

A chanrcl may be placed in an inoperable status for up tr 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for b.

required surveillance without placing the trip system in the tripped condition provided at least one other OPEPASLE channel in the same trip systen is monitorina that parameter.

With a design providin; only one channel per trip system, an inoperable c.

channel need not be placed in the tripped condition where this would cause In these cases, the inoperable channel shall the Trip Function to o cur.

be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken, d.

Trips the mechanical vacuum pumps.

A channel is OPERAELE if 2 of 4 instruments in that channel are OPERABLE.

e.

May be bypassed with reactor steam pressure ; 1043 psig and all turbine f.

cton valves closed.

f.s c n ly F".C vo' sciation valve 2^31-FF "

h

t. i a m only 1,

0 jL5tAle UD IC C.

.it5 kb J

HATCH - (11T 2 3/4 3-15 Arendrent No.

TABLE 3.3.2-2 E

ISOLATION ACTUATION It4STRU'1ENTATION SETPOINTS N

~

ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE F

Z l.

PRIl'ARY CONTAINMENT ISOLATION m

a.

Reactor Vessel Water Level 1.

Low

> 12.5 inches *

> 12.5 inches

2.

Low Low

[-39 :nches*

{-38 inches

b.

Drpell Pressure - liigh

< 2 psig

< 2 psig c.

thin Steam Line 1.

Radiation - liigh

< 3 x full power background

< 3 x full power fiac.kground 2.

Pressure - Low t 825 psig

825 psig

_u 3.

Flow - liigh

< 140% of rated flow

< 140% of rated flow n

d.

fiain Steam Line Tunnel w

y Temperature - High

< 200*F

< 200 F e.

Condenser Vacuum - Low

> 7" lig vacuum

> 7" Hg vacuum f.

Turbine Building Area Temp.-liigh

<2do'F

< 200*F 7

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - High

< 60 nrf r**

< 60 mr/hr**

b.

Drywell Pressure - liigh

< 2 osig

< 2 psig CN m,

c. Reactor Vessel Water Level - Low

> 12.5 inches *

> 12.5 inches

N

d. Refueling Floor Exhaust U'

g

-< 20 nr/hr**

Radiation - High T See Bases Fiqure 2 3/4 3-1.

Initial setpbitt.

Fi"al setpoint to be detemined during startup testing.

3/4.0 APPLICABILITY.

BASES The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveil-lance Requirements within Section 3/4.

3.0.1 This specification states 'the applicability of each specifi-cation in terms of defined OPERATIONAL CONDITION and is provided to Jelineate specifically when each specification is applicab'.e.

3.0.2 This specification defines those conditions necessary to constitute compliance with the ten s of an individucl Limiting Condition for Operation and associated ACTION requirement.

3.0.3 This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements and whose occurrence would violate the intent of the specification.

For example,

Specification 3.5.1 calls for the HPCI to be OPERABLE and specifies explicit requirements if it become inoperahle.

Under the terms of Specifi-cation 3.0.3 if the required additional systems are not OPEPABLE, the facility is to be placed in HDT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and be in

^0LD SHUTD0'."' within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The unit shall be brought to j

-0T SHUID0'.7, and COLD SHUTDOVi within the required times by pronptly initiating and carrying out an orderly shutdown.

It is intended that thi o cuidance also apply whenever an ACTION statement requires a unit to be in (at least) STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or in (at least) HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3.0.4 This specif;;ation provides that entry into an OPERABLE CONDITIO',' mus t be m34 vi th (a) the full complement of required systens, equipment or components CPERAELE and (b) all other parameters as specified in the Limiting Conditions for Operation being met without regard for allowable deviations and out of service provisions contained in the ACTION statements.

The intent of this provision is to insure that facility operaticn is not initiated with either required equipment or systens inoperable or other linits being exceeded.

F>ceptions to this prevision have been provided for a limited number af specifications when startuo with inoperable equipment would not af fect alant safety.

These exceptions are stated in the ACTION statements of the

ppropriate specifi;aticns.

+',TCH - UNIT 2 B 3/4 0-1

/cendment,No. < g 40u c-

_ APPLICABILITY BASE 5 4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Opera *. ion are met and will be perfomed during the OPERATIONAL CONDITIONS for which the Limiting Conditions for Operation are applicable.

Provisions for additional surveil-lance activities to be performed without regard to the applicable OPERA-TIONAL CONDITIONS are provided in the individual Surveillance Requirements.

4.0.2 The provisions of this specification provide allowable toler-ances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and perfomance considerations.

The phra:c "at least" associated with a surveillance frequency does not negate this allowable tolerarne value and permits the performance of more frequent surveillance activities.

The tolerance values, taken either individually or consecutively over three test intervals, are sufficiently restrictive to ensure that the reliability associated with tbe surveilla'nce activity is not significantly degraded beyond that obtained from the nominal specified interval.

4.0.3 The provisions of this specification set forth the criteria for deterrination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation.

Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveil-lance activities have been Latisf actorily performed within the specified tire interval.

Nothin; in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requiremr.its.

4.0.4 This specification ensures that surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an applicable CONDITION, The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Liniting Condition for Operation.

$b5 2

HATCH - UNIT 2 B 3/4 0-2

ML19241C132

Text

Navigation menu

Search