Text

Proposed Tech Specs,Proposing Overall Conversion of Current PBAPS TS to Improved TS as Contained in NUREG-1433, Std TS, GE Plants,BWR/4
	ML20086Q465
Person / Time
Site:	Peach Bottom
Issue date:	07/21/1995
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20086Q430	List: ML20086Q427; ML20086Q465;
References
	RTR-NUREG-1433 NUDOCS 9507280054
	Download: ML20086Q465 (25)
	v • d • e

'

Primary Containment Isolation Instrumentation 3.3.6.1 (V~')

SURVEILLANCE REQUIREMENTS

.....__........___......____...___---NOTES------------------------------------

1.

Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains primary containment isolation capability.

4 SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.1.3

NOTE-------------------

O For Function 1.d radiation detectors are excluded.

Perform CHANNEL CALIBRATION.

92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.

18 months

/(\\s SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.6.1.6 Calibrate each radiation detector.

24 months SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months i

O PBAPS UNIT 2 3.3-51 Amendment 9307280054 950721 PDR ADOCK 05000277 P

PDR

1

.f,

Organization 5.2

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-5.2 Organization X

5.2.2 Unit Staff (continued) 3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time;

}

4.

Except during' extended shutdown periods, the use of l

overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized j

in advance by the Plant Manager or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting l

the deviation.

i Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to ensure that excessive hours have not been assigned. Routine deviation from the above

+

guidelines is not authorized.

f.

The Senior Manager-0perations or an Operations Manager shall I

hold an SRO license.

g!

g.

The Shift -Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. When the STA position is filled by an on-shift SRO, the minimum shift crew composition shall include a minimum of 3 SR0s.

In addition, the STA or the individual filling the STA position shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

I I

O PBAPS UNIT 2 5.0-4 Amendment 2

i Primary Containment Isolation Instrumentation 3.3.6.1

)

SURVEILLANCE REQUIREMENTS (V

_______.....____.......________-NOTES------------------------------------

1.

Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains primary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.1.3

NOTE-------------------

O)

For Function 1.d, radiation detectors are excluded.

~-

Perform CHANNEL CALIBRATION.

92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.

18 months

/hi SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.6.1.6 Calibrate each radiation detector.

24 months SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months l

PBAPS UNIT 3 3.3-51 Amendment

Organization

.l 5.2 f'

5.2 Organization V;

5.2.?

Unit Staff (continued) 3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time; 4.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized in advance by the Plant Manager or his designee, in 4

accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

f.

The Senior Manager-0perations or an Operations Manager shall (q) hold an SRO license, The Shift Technical Advisor (STA) shall providb advisory g.

technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. When the STA position is filled by an on-shift SRO, the minimum shift crew composition shall include a minimum of 3 SR0s.

In addition, the STA or the individual filling the STA position shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

v PBAPS UNIT 3 5.0-4 Amendment

I:.

i Prinary Containment Isolation Instrumentation

)

B 3.3.6.1

(

BASES L) i SURVEILLANCE SR 3.3.6.1.2 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant i

specific setpoint methodology.

l The 92 day Frequency of SR 3.3.6.1.2 is based on the i

reliability analysis described in Reference 7.

SR 3.3.6.1.3. SR 3.3.6.1.4. SR 3.3.6.1.5. and SR 3.3.6.1.6 A CHANNEL CALIBRATION is a complete check of. the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the assumptions of the current setpoint methodology. SR 3.3.6.1.6, however, is only a calibration of the radiation detectors using a standard

(

radiation source.

As noted for SR 3.3.6.1.3, the main steam line radiation detectors (Function 1.d) are excluded from CHANNEL CALIBRATION due to ALARA reasons (when the plant is operating, the radiation detectors are generally in a high radiation area; the steam tunnel). This exclusion is acceptable because the radiation detectors are passive devices, with minimal drift. The radiation detectors are calibrated in accordance with SR 3.3.6.1.6 on a 24 month i

Frequency.

The 92 day Frequency of SR 3.3.6.1.3 is conservative with Ib respect to the magnitude of equipment drift assumed in the setpoint analysis.

The Frequency of SR 3.3.6.1.4 is based on the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the b

setpoint analysis.

The Frequencies of SR 3.3.6.1.5 and SR 3.3.6.1.6 are based on the assumption of a 24 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

(continued) 3 PBAPS UNIT 2 B 3.3-166 Revision 0 i

c Primary Containment Isolation Instrumentation B 3.3.6.1 I

'i BASES wJ SURVEILLANCE SR 3.3.6.1.2 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day Frequency of SR 3.3.6.1.2 is based on the reliability analysis described in Reference 7.

SR 3.3.6.1.3. SR 3.3.6.1.4. SR 3.3.6.1.5. and SR O.6.1.6 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the assumptions of the current setpoint methodology.

SR 3.3.6.1.6, however, is only a q

calibration of the radiation detectors using a standard Q

radiation source.

As noted for SR 3.3.6.1.3, the main steam line radiation detectors (Function 1.d) are excluded from CHANNEL CALIBRATION due to ALARA reasons (when the plant is operating, the radiation detectors are generally in a high radiation area; the steam tunnel). This exclusion is acceptable because the radiation detectors are passive devices, with minimal drift. The radiation detectors are calibrated in accordance with SR 3.3.6.1.6 on a 24 month Frequency.

The 92 day Frequency of SR 3.3.6.1.3 is conservative with N

respect to the magnitude of equipment drift assumed in the setpoint analysis.

The Frequency of SR 3.3.6.1.4 is based on the assumption of an 18 month calibration interval in the A

determination of the magnitude of equipment drift in the setpoint analysis. The Frequencies of SR 3.3.6.1.5 and SR 3.3.6.1.6 are based on the assumption of a 24 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

(continued) l PBAPS UNIT 3 8 3.3-166 Revision 0

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l fty Staff e-The if;q'Af organization shall 5:sho G %k.h.. the following:

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@ @rarh an dutv <hiftigwn in Table 6.2.

l be compose f at le e minim hift

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th the shift ew

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\\ompos~itionsho composition may oc less than the minimum requirementsifor a ceriod 3

of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected E d ' 'NM0 absence of on-duty shift crew members provided immediate action bb)W%

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is taken to restore the shift crew composition to within the A

minimum requirements.

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At least one licensed operator shall be in the control room and assigned to each reactor that contains_ fuel. t M,

..f AkG At least two licensed operators,pe ;..;;;.; ;r.;R lag;.,.h 0[5 l

pn _ _.

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An individual qualified in radiation protection erocedurer shall.

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y on 4 +. ms -- in.1 is in the reacteva'In.,44 4 4 w.r.r M wg,

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o., m,.a., +.r -verM aw.= est 4.s i-u.y p; u6 4.4u n. m..,.a x4,

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All GUKL All IUnd shall De tractly superY15e y e1Lntr a icensed Senior actor Operator Senior Reactor 0 ator j

L ited to Fuel Ha ling who has n other concurrent naa-sib ity during this eration.

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In addition to the requirements of 6.2.2.a. the Senior Manager-4 Operations shall hold a Senior Reactor Operator license t

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The rganization shall ' ""- ' ' the following:

Each on-duty shifi ghal e composed o t least.tnebinimum shif t Y'

wamaasition % own a 6.2.1.

t that t ift crew i

grew composition say be less than the minimum requirements 6 tor a certo<

rof 10cF4.

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of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accosmodate unexpectet '

absence of on-duty shift crew members provided immediate action 5' *' M i

is taken to restore the shift crew composition to within the biCM minimum requirements.

r,2.r.er b.

At least one licensed operator shall be in the control room and p,

assigned to each reactor that contains fuel.j T #,.,k;d,,

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At least two licensed operators, ave""

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--M, shall be present in the control room duringhj '"%ea um l

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An individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor. =

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11 CORE ALTEwl 5 shall ne cirectly ervised by either al censed Senior Reac r Operator or Senior ctor Operator l

Li ted to Fuel Handl who has no other con rrent responQ sibi ity durino this oc tion.

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4 m.w(S) i In addition to the requiremerits of 6.2.2.a. the Senior Manager-e, Operations shall hold a Senior Reactor Operator licenseg j

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-244 A.and=e= No. M. 68, Z22.135, If 7,190,198 fy4 o

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DISCUSSION'0F CHANGES ITS 5.0: ADMINISTRATIVE CONTROLS.

o-TECHNICAL CHANGES - LESS RESTRICTIVE' (continued)

E The proposed change will revise the requirement for the Senior s

Manager-Operations to hold a Senior. Reactor 0perator (SRO) license.

The change will require the Senior Manager-Operations or an Operations Manager to hold an 'SRO license.

The current. PBAPS.

.3 Operations organization management structure 'is comprised of the Senior Maaager-Operations and two Operations Managers. In order to comply with the requirements specified in proposed Specification 5.2.2.f, one of these individuals will be required to hold ap SRO-

-i license. Therefore, in the event the Senior Manager-Operations does not hold an SRO license, then an Operations Manager must hold an SRO.

license.

This individual will 1) be qualified to. fill the Senior l

Manager-Operations position, 2) have the same management authority

-l over the licensed operators as the Senior Manager-Operations, and 3) be designated in Administrative procedures.as holding an SRO -

i license.

Designating the specific Operations Manager required.to hold an SRO license in Administrative procedures assures that there-t is always an individual holding a current SRO license in one of the Operations management positions.

l t

L Existing Specification 6.13, which provides high -radiation area 6

access control alternati'ves pursuant to 10 CFR 20.203(c)(2) (revised O

10 CFR 20.1601(c)), has been significantly revised-as a-result of the changes to 10 CFR 20, the guidance provided in Regulatory Guide; 8.38 (Control of: Access to High and Very High Radiation Areas in l

Nuclear Power Plants). -and current industry technology in'

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controlling access.to high radiation areas. The changes include a i

capping dose rate to differentiate a.high radiation area from a very i

high radiation area,. additional requirements for groups. entering 1

high radiation. areas, and clarification' of the need for communication and control of workers in high radiation areas.. This change provides acceptable alternate methods for controlling access i

to high radiation areas. As a result, this change will not decrease the ability to provide control of exposures from external sources in restricted areas.

t

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i PBAPS UNITS 2 & 3 20 Revision 0

/

i.

NO SIGNIFICANT HAZARDS CONSIDERATIONS

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(

CHAPTER 5.0--ADMINISTRATIVE CONTROLS G'

TECHNICAL CHANGES - LESS RESTRICTIVE (continued)

(L5 Labeled Comment / Discussion for ITS 5.0)

The proposed change will revise the requirement for the Senior Manager-0perations l

to hold a Senior Reactor Operator (SR0) license.

The change will require the Senior Manager-Operations or an Operations Manager to hold an SR0 license. The current PBAPS Operations organization management structure is comprised of the Senior Manager-0perations and two Operations Managers. In order to comply with j

the requirements specified in proposed Specification 5.2.2.f, one of these L

individuals will be required to hold an SR0 license. Therefore, in the event the l

Senior Manager-0perations does not hold an SR0 license, then an Operations Manager must hold an SRO license. This individual will 1) be qualified to fill b

the Senior Manager-Operations position, 2) have the same management authority over the licensed operators as the Senior Manager-0perations, and 3) be designated in Administrative procedures as holding an SR0 license. Designating the specific Operations Manager required to hold an SR0 license in Administrative procedures assures that there is always an individual holding a current SRO license in one of the Operations management positions.

PECO Energy has evaluated this proposed Technical Specification change and has determined that it involves no significant hazards consideration.

This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92. The following evaluation is provided for the three categories of fa the significant hazards consideration standards:

1.

Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

Revising the requirement for the Senior Manager-0perations to hold an SR0 license will not increase the probability or consequences of an accident previously evaluated. The change is an administrative change that has no impact on the accident precursors of any PBAPS UFSAR Chapter 14 accident since the proposed change will still require the Senior Manager-0perations or an Operations Manager having the same management authority over the 4

licensed operators as the Senior Manager-0perations to hold an SR0 license.

Therefore, this change will not involve a significant increase in the probability or consequences of an accident previously evaluated.

2.

Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

This change will not physically alter the plant (no new or different type of equipment will be installed). The changes in methods governing normal plant operations are consistent with current safety analysis assumptions.

Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated.

PBAPS UNITS 2 & 3 32 Revision 0

/.-

-c NO SIGNIFICANT HAZARDS CONSIDERATIONS G)

CHAPTER 5.0--ADMINISTRATIVE CONTROLS

/

TECHNICAL CHANGES - LESS RESTRICTIVE (L Labeled Comment / Discussion for ITS 5.0) - continued 5

3.

Does this change involve a significant reduction in a margin of safety?

The proposed change will require either the Senior Manager-0perations or l

one of the Operations Managers to hold an SR0 license.

The Operations Manager who holds the SR0 license, when the Senior Manager-0perations does A

not hold an SR0 license, will be qualified to fill the Senior Manager-

/o\\

Operations position and will have the same management authority over the licensed operators as the Senior Manager-Operations.

Therefore, operations shift personnel will continue to be managed by an SR0 licensed individual.

In addition, this change is expected to have an overall lA positive impact on safety by enhancing the Senior Manager-0perations ability to effectively carry out his primary responsibilities and by improving the consistency and continuity of managerial oversight for Operations personnel.

Therefore, this change does not involve a significant reduction in a margin of safety.

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i PBAPS UNITS 2 & 3 33 Revision 0 I

, ~ -

1 Primary Cantainment Isslatian Instrumentation 3.3.6.1

^

SURVEILLANCE AEQUIREMENTS l

t O ;c J

..................................N0TES....................................

1. - Refer to' Table 3.3.6.1 1 to determine which SRs apply for each Primary -

Containment Isolation Function.

2. ' When a channel is placed. in an inoperable status. solely for perfomance of i

required Surveillances, entry into associated Conditions and Required' Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains primary containment isolation capability..

l

-i SURVEILLANCE FREQUENCY-SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

1 i

t SR 3.3.6.1.2 Perfom CHANNEL FUNCTIONAL TEST.

492[ days

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. Celi' 6. Ms.E{i,..:it.

[*2] d y-SR.3 3.5.1.2.

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f...- =ewT-.

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A N,se.a n.t,%. w n.ow.re m.u.k.g.,.

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1 1

SR 3.3

.f Perfom CHAnnu. CALIBRATION.

92 days I

$ ;: t y

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a *: = C'ffr:L ; s i E+.--

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SR 3.3 Perfom CHANNEL CALIBRATION.

s SR 3.3.6 1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST.

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BWR/4 STS 3.3 54 i

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.: t DISCUSSION OF CHANGES TO NUREG-1433 i

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C'Q SECTION 3.3 -- INSTRUMENTATION i

NON-BRACKETED PLANT SPECIFIC' CHANGES (continued)

=

P SR 3;3.6.1.4 (18 month Channel Calibration) was=added for Function-h g

2.c.. SR 3.3.6.1.6 (24 month calibration of radiation detectors) was

.j added for Function 1.d and the Note to NUREG SR 3.3.6.1.4 was _added j

toL exempt the radiation - detectors from the Channel Calibration requirements.

These changes are; based on' PBAPS plant specific design and setpoint analysis.

-P, Function 1.d'was added to the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A0T for Action A.whi'ch is-i i

consistent with NEDC-31677P-A and NEDC-30851P-A. Also Function'6.b.

was deleted because this Function is not-common to the RPS.

l P,

This change proposes to add new Functions to Table 3.3.6.1-1, "PCI t

3 Instrumentation."

Function 1.d, Main Steam Line-High Radiation; j

function 2.c, Main Stack Monitor Radiation-High; Function 3.b. HPCI j

Steam Supply Line Flow - Time Delay Relays; Function 4.b, RCIC Steam Line F'ou - Time Delay Relays; and Function 7.a Reactor Pressure-High. Also, some of Functions listed in the NUREG-1433 Table were i

deleteo because PBAPS does not have the instruments. As'a result of the addition and deletion of Functions, other changes in-the Table were made for -consistency (e.g.,

Footnotes being deleted, 4

Surveillances being deleted, etc.). These changes were made based on the PBAPS plant specific design.

j O

Ps The specific values will be relocated to the COLR. This~will help eliminate the number of Technical Specification changes required due 1

to these values changing.

The COLR is a controlled. document in which any changes made to it will required a review in accordance

.I with 10 CFR 50.59. This change is based on PBAPS Amendment No. 184 for Unit 3, dated 9/14/93. The Amendment for Unit 2 will be issued

_ i prior to Unit 2 refuel outage scheduled for' the Fall of 1994 (as--

i stated in the NRC.SER for Unit 3 dated 9/14/93).'

P This Specification was deleted because the Instrumentation does not i

33 exist at PBAPS.

This change is based on the PBAPS plant specific

.i design.

1 P

The changes made to this Specification reflect that the only MCREV az Instrumentation is the Control Room Air Intake Radiation Monitoring 1

Instrumentation. The LCO, Applicability,' Actions, and Surveillance _

Requirements were modified to reflect this, and Table 3.3.7.1-1 was deleted. This change is based on the PBAPS. plant' specific design..

Also the Completion Time for proposed. Action A.2 is 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is consistent with NUREG-1433, Required. Action C.2 l

Completion Time, which is the proper time for the instrument.

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- PBAPS UNITS 2 & 3 7

Revision 0 l

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m,(J t-Organization 5.2 i

5.2 Organization j

5.2.2 Unit Staff (continued) 3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between i

work periods, including shift turnover time; 4...-

4.

Except during extended shutdown periods, the use of overtime should be considered on an individual bas'is

~

and not for the entire staff n a shi i

s v-e Any deviation from the above ui e sha be authorized

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in advance by the4 Plant sic;r=.;; d;r)j%r his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established A

M procedures and with documentation of the basis for granting A -

the eviat on.

user a

cohirois s all be included in the procedures such that t

individual overtime shall be reviewed monthly by theJPlant

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2:::: ]$4er his designee to ensure that excessive hours nave not been assigned. Routine deviation from the abo a guidelines is not authorized.

93 O.

The amount of overtime worked by unit staff members performing safety related functions shall be limited and controlled in accordance with the NRC Policy Statement on g

working hours (Generic Letter 82-12).

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f.

The ib;r: tier: 5:i;:for M6t::? Operation Managerf A

old an SRO license.

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The Shift Technical Advisor (STA) shall provide advisory 4 % *a5 technical support to the Shift Supervisor (SS) in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit i

y BWR/4 STS 5.0-4 Rev. O,09/28/92 O

DISCUSSION OF CHANGES TO NUREG-1433 (v})

CHAPTER 5.0 -- ADMINISTRATIVE CONTROLS NON-BRACKETED PLANT SPECIFIC CHANGES (continued)

P This change modifies requirements for leak testing primary coolant io sources outside containment to limit tests to the extent permitted by system design and radiological controls.

This change is consistent with the PBAPS current Technical Specification requirements.

P This change to Section 5.5.4.e (old 5.4.2.4.e) modifies the n

requirement to determine cumulative dose from effluents such that only liquid effluents must be considered. This change is consistent with existing Technical Specification requirements.

P Not used.

k u

P The overtime limit requirements have been revised to delete the u

reference to the length of the work day "[8 or 12] hour day".

However, the nominal 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months work week requirement will still be maintained. This wording is being deleted in order to provide more flexibility in shift scheduling to allow shifts up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The proposed change does not change the intent of the guidance of Generic Letter 82-16 with regards to the number of hours worked per a

week, and will ensure that routine use of heavy overtime will not be Q

used.

P Not used.

b u

ld P

Not used.

u p+)

V PBAPS UNITS 2 & 3 4

Revision 0

pe e

Primary Ctntainment'!sslatien Instrumentatitn B 3.3.6.1 TD' BASES SURVEILLANCE OR :.7-A 1 7 and SR 3. 3 fi.1 A t - _ti =7 -

REQUIREMENTS sodgmE!i.nd U,e ;slietilit,H ^ -si th: :-

a+- (ti : d: P j

.4..hi t =f -f = ? d-"

w..,,

75R /3.3.6.1.3 j

M li ation of trip uni provides check of e actua tri setpoin. The ch nel must declared operable f e_ >

t trip se ing is scovered t be less e servative han

'D/

e Allow e value pecified Table 3.

.1-1.

I the' trip set ng is d covered to e less co ervative an account d for i the approp ate setpo t methodo gy, but is no beyond e Allowabl Value, t channel p orsane is s 11 wit n the requ nts of he plant fety e

ana ysis, nder these onditions, he setpoi must b rea juste to be equa to or ao conservati e than at accounte for in the ppropriat setpoint thodolo The Frequency of 92 days is b ed ort the liabil ty

)

. (analysis.of..Refe_r.ences. 5 and 6..

~k SR 3.3.6.1 eneSR 3.3.6.1 gg 3 3.p.( c4 50.3.(,f. f.

N 3*M*M'**"%

A CHANNEL CALIBRATION is a complete check of the instrument

h * **C WG et loop and the sensor. This test verifies the channel

'5 *

'* h% + 6 A%n responds to the measured parameter within the necessary 4%,. sA,Q range and accuracy. CHANNEL CALIBRATION leaves the channel m'

rcW %,

adjusted to account for instrument drifts between successive

.. p.,.i. q.. hi;teri;;I ^

a11brationsg;;....y..

.o.

(ch. ".. "' M I"" C_ 'LR. - 3'. M..",,' '.' '.'*".* 2.."..". 7 ". 2.

f..' ". " %

..$ j u.

iiint d consistent with the assumptions of the etpoint

/.

thodology.,

urre 3'

If e as ound etpoint is not w thin its requi. 4 1

ble alue, the pla t speci ic setpoi meth ology may

)

h revis d, as ppropri e, if e history and al other

/

pertine t info tion dicate a need fo the ision. Th setpo t shal be lef set co istent h the ssumptions (of t _ curre t plant pecifi setpoint thod ogy.

[{-

M/*Th)Freque 3.3.6. Y M @::d - th; e;;,.tien ;'*

-m UV4 ';

J., s. nin. U... inte; el n th: d:t: =i nti n ;' th; "

(continued) s

+

BWR/4 STS B 3.3-180 Rev.

O, 09/28/92 i

l N

Primary Containment Isolation Instrumentation 5 3.3.6.1 CJ

.2 776.i.

~

3/

p.u g u

sEs-SURVEILLANCE SR 3.3.6.1.7 nd SR 3.3.6.1.8 /(c'ontinued REQUIREMENTS go ae g magnitude of equipment dr in theesetpoint analysis.

Frequency of SR 3.3.6.1 46-on the assumption of hf" 2 month calibration interval-in the detemination of th magnitude of equipment drift in the setpoint analysis.

SR' 3.3.6.1.7 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the a

OPERABILITY of the required isolation logic for a specific channel. The system functional testing perfomed on PCIVs -

in LCO 3.6.I.3 overlaps this Surveillance to provide -

complete testing of the assumed safety function.

-.m r

uency is o en on Ine... to pe m th g go.n.s.7 etilance der the e ditions t t apply du ng a a

e and t potential r an unpla ed transie t if 4

H 11 mars no t nerf.. _-- 4th the eter at a e

al Aperating experience has shown these c ents rrr ?.f pass.

he Survei lance when performed at the nth Frequency.

g g l

I SR 3.3.A'.1.X I

Thi R ens s that indi ual chann respon times a

less n or 1 to t maximum v es ass d in the i

ciden analysi. The i rument re nse ti must be V'd added o the closu times to sin the 0 TION f

SYS RES TIME.

A/.N k

A t4 c.I LATI SYSTEM R PONSE TIME ccep anc criter' e

i includ in Refe ce 7.

Th test may perfo d in one i

y meas nt, o in overlap ng segmen, with ve fication t

all e nents are sted.

A Note t he Surveil nce states hat the r fation detecto may be es uded from LATION SY EM RES SE TIME sting. Thi Note is nec sary beca e of the i

dif culty of g erating an propriate tector i put

.{

i s

al and use the prin pies of de ctor o ation rtually e re an insta aneous res nse ti Respon times for diation det or channel shall measure from detecto output or the nput of th first el ctronic k

i d omponent in the cha el.

J (continued)

BWR/4 STS 8 3.3 181 Rev. 0 09/28/92 1%

G s se m.i.9 a wa N =. y.,. nssqb cf-ex is*M

- 7 f

ca

cAA, 64 A

A hAA g

~

ddt.

ep-d 4A

~AA 4

% se, i.h twsd.s (in y

. -.

ML20086Q465

Text

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