Text

Amend 164 to License DPR-20,allowing one-time Deferral of Several 18-month Interval Surveillance Tests Until Scheduled Refueling Outage
	ML20082M724
Person / Time
Site:	Palisades
Issue date:	04/20/1995
From:	Kennedy J; NRC (Affiliation Not Assigned)
To:	;
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ML20082M726	List: ML20082M724; ML20082M732;
References
	NUDOCS 9504240355
	Download: ML20082M724 (18)
	v • d • e

i p er; 21 UNITED STATES p

E NUCLEAR REGULATORY COMMISSION f

WASHINGTON D.C. ace 864001

.....l' CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-20 1.

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

A.

The application for amendment by Consumers Power Company (the licensee) dated February 10, 1995, as supplemented March 27 and March 30, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission'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; E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-20 is hereby amended to read as follows:

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9504240355 950420 DR ADOCK 05000255 PDR

4,

Technical Soecifications l

The Technical Specifications contained in Appendix A, as revised through Amendment No. 164, and the Environmental. Protection Plan contained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Jouf L. Lu4 Janet L. Kennedy, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications i

Date of Issuance: April 20, 1995 1

I i

i

4 ATTACHMENT TO LICENSE AMENDMENT NO. 164 FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

REMOVE INSERT 4-6 4-6 4-71 4-71 4-71a 4-72 4-72 4-73 4-73 4-74 4-74 4-74a 4-74a 4-76 4-76 4-77 4-77 4-78 4-78 4-79 4-79 4-80 4-80 4-81 4-81 4-82 4-82

4.1 DVERPRESSURE PROTECTION SYSTEM TESTS Surveillance Reouirements In addition to the requirements of Specification 4.0.5, each PORV flow path shall be demonstrated OPERABLE by:

1.

Testing the PORVs in accordance with the inservice inspection requirements for ASME Boiler and Pressure Vessel Code,Section II, Section IWV, Category B valves.

2.

Performance of a CHANNEL CALIBRATIO at least once per 18 months *.

3.

When the PORY flow path is required to be OPERABLE by Specification 3.1.8.1:

(a) Performing a complete cycle of the PORV with the plant above j

COLD SHUTMWN at least once per 18 months.

(b) Performing a complete cycle of the block valve prior to heatup from COLD SHUTDOWN, if not cycled within 92 days.

4.

When the PORV flow path is required to be OPERABLE by Specification 3.1.B.2:

(a) Performance of a CHANNEL FUNCTIONAL TEST on the PORV actuation channel, but excluding valve operation, at least once per 31 days.

1 4

(b) Verifying the associated block valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

i 5.

Both High Pressure Safety Injection pumps shall be verified incapable of injection into the PCS at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , unless the reactor head is removed, when either PCS cold leg temperature is <300'F, or when both shutdown cooling suction valves, MD-3015 and MO-3016, are open.

B1111 4

With the reactor vessel head installed when the PCS cold leg temperature is less than 300*F, or if the shutdown cooling system isolation valves MO-3015 and MO-3016 are open, the start of one HPSI pump could cause the Appendix G or the shutdown cooling system pressure limits to be exceeded; therefore, i

both pumps are rendered inoperable.

l For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12.

Amendment No. 130, I'?, 150, M B,g s

164, 4-6

4.16' INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (Snubbers)

Acolicability

~

Applies to periodic surveillance of safety-related snubbers as described per Specification 3.20.

4.16.1 Snecifications

(

Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program in addition to the requirements of Specification 4.0.5.

As used in this specification,

" type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.

a.

Visual Insoection Snubbers are categorized as inaccessible er accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the following paragraph:

If one or more unacceptable snubbers are found, the next inspection interval shall be 2/3 (-25%) of the previous interval.

If no unacceptable snubbers are found, the next interval may be doubled

(-25%), but not to exceed 48 months.

The interval extension provisions of Technical Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.

Inspections performed before the interval has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early inspections, performed before the original required time interval has elapsed (nominal time less 25%), may not be used to lengthen the required inspection interval.

Any inspection whose results require a shorter inspection interval will override the previous schedule.

b.

Visual Insoection Acceptance Criteria Visual inspection shall verify that (1) the snubbar has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional. Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the causa of the rejecticn is clearly established and remedied for that particular snubber and for other snubbers, irrespective of type, that may bc generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Technical Specificatien 4.16.ld or 4.16.le, as applicable. All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval.

4-71 Amendment No, M, 69, 4W, 448,164

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4.16 INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS fSnubbers) 4.16.1 b.

. Visual Insoection Acceotance Criteria (continued)

A review and evaluation shall be performed and documented to-justify continued operation with an unacceptable snubber.

If continued operation cannot be justified, the snubber shall be declared inoperable and the action requirements shall be met.

c.

Functional Tests

At least once per 18 months during shutdown, a representative sample (10% of the total safety-related snubbers in use at the plant) shall be functionally tested either in place or in a bench test. The test shall verify the snubber has freedom of mvement and is not frozen up.

For each snubber which did not meet the functional test acceptance criteria of Specification 4.16.1.d or 4.16.1.e l

tested."g an additional 10% of the total shall be functionally The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.

Snubbers identified as especially difficult to remove or in high radiation zones during l

shutdown shall also be included in the representative sample.i2 In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.

If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for the resampling.

If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place,.the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

l Snubbers of rated capacity greater than 50,000 pounds are not to be included when defining the total number of safety-related snubbers in use at the plant.

l Permanent or other exemptions from functional testing for individual snubbers may be granted by the Commission only if a justifiable basis for exemption it presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at i

either the completion of their fabrication or at a subsequent date.

For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12.

l 4-72 Amendment No. 107, 148, 164

4.16 INSERVICE INSPECTION PROGRAM FOR SHOCK SUPP'dSSORS (Snubbersi 4.16.1 c.

Functional Tests * (continued)-

l

$nubbers of rated capacity greater than 50,000 pounds will be.

functionally tested in lots comprising 25% of their total during each refueling outage.

In the event of one snubber failure out of the four tested, no additional snubbers will be tested provided the problem is non-generica For each additional snubber failure, however, two additional snubbers will be tested until no further snubber failures are identified or all snubbers have been tested.

Generic failures will be handled as the specific circumstances require.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are suppressed by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components suppressed by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the suppressed component remains capable of meeting the designed service.

d.

Hydraulic Snubber:i Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1.

Activation (restraining action) is achieved within the specified range of velocity or accelerati:nt in both tension and compression.

2.

Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

e.

Pechanical Snubbers Functional Test Acceptance Criteria 1

The mechanical snubber functional test shall verify that:

1.

The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force (break away friction).

2.

Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

3.

Snubber release rate, where required, is within the specified i

range in compression or tension.

For snubbers specifically required not to displace under continuous load, the ability-of the snubber to withstand load without displacement shall be i

verified.

For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12.

Amendmer.t No. 69, 93, 107, 164

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]~4.16 INSERVICE INSPECTION-PROGRAM'FOR SHOCK SUPPRESSORS (Snubbers) f 4.16.1 f.

Snubber Service Life Monitorina-l designated service life commences and the installation and.

A record of the service life of each snubber,-the date at which'the maintenance records on which the designated service life is based I

shall.be maintained as required by Specification 6.10.2.1.

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each safety related snubber in use 'in the plant shall

l be reviewed to verify that the indicated service life has not been-

'1 exceeded or will not be exceeded prior to the next scheduled I

service life review.

If the indicated service life will be i

- exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend'its-service life beyond the date of the next scheduled service life review. This re-evaluation, replacement or reconditioning shall be indicated in the records.

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4-74 Amendment No. M, 69, M, 4W,164 i

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J 4.16 INSERVICE INSPECTION PROGRAM FOR SH0CK'SUPPRESSORS fSnubbers) 4.16 Raili a

1 The visual inspection frequency is. based upon maintaining a constant' level of t.

' snubber prote tion to. systems. Therefore, the required inspection interval varies inverseiy e th'the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may. be-used as a r.w reference point to determine the next inspection. However, the results of such early i

inspections, performed before the original required time interval has elapsed l

(nominal time less 25Y.) may not.be used to lengthen the required -inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

l t

When the cause of the rejection of a snubber is clearly established.and.

I remedied for the snubber and for any other snubbers that may be generically.

susceptible, and verified by inservice functional, testing, that snubber may i

be exempted from being counted as inoperable. ' Generically susceptible j

snubbers are those which are.of a specific make'or model and have the same i

design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation and vibration.

When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely l

affected by the inoperability of the snubber.

The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers, excluding snubbers of rated capacity greater than 50,000 pounds, will be functionally tested at 18 month intervals. A representative sample of snubbers of rated capacity greater than 50,000 pounds will be functionally tested each refueling outage.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and a"ociated installation and maintenance records (newly installed snubber, s

1 replaced, spring replaced, in high radiation area, in high-temperature area, etc...).

The requirement to monitor the snubber service life.is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

4-74a l

Amendment No. H, 69, M7, 164

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4.17. INSI'RUMENTATION SYSTEMS TESTS Table 4.17.1 Instrumentation Surveillance Reautrements for j

Reactor Protective System l

CHANNEL CHANNEL FUNCTIONAL CHANNEL Functional Unit CHECK TEST CALIBRATION 1.

Mar.isal Trip NA (a)

NA l

2.

Variable High Power -

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days (b, c, & d) 3.

High Start Up Rate 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (a) 18 months

r l 4.

Thermal Margin /

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months'*

i Low mressure l 5.

High Pressurizer 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

Pressure i

l 6.

Low PCS Flow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months *

(

7.

Loss of Load NA (a) 18 months l 8.

Low "A" SG Level 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

I

- l 9.

Low "8" SG Level 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months *'

j l 10. Low "A" SG Pressure 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

l 11. Low '8" SG Pressure 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months *

]

12. High Containment Pressure NA 31 days 18 months

13. RPS Matrix Logic NA 31 days NA

14. RPS Initiation Logic NA 31 days NA

15. Thermal Margin Monitor; Verify constants each 92 days.

{

(a) Once within 7 days prior to each reactor startup.

(b) Calibrate with Heat Balance each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , when > 15% RATED POWER.

(c) Calibrate Excores channels with test signal each 31 days.

l (d) CHAMBEL CALIBRATION each 18 months.

(e)

Include verification of automatic Zero Power Mode Bypass removal.

i t

For Cycle 11 only, this surveillance need not be performed until prior to i

startup for Cycle 12.

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Amendment No. MS, MG, M6, MG, M3,164 4-76 i

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4.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.2 Instrumentation Surveillance Reauirements for Enaineered Safety Features CHANNEL CHANNEL FUNCTIONAL CHANNEL Functional Unit CHECK TEST CALIBRATION 1.

Safety In.iection Sianal (SIS) a.

Manual Initiation NA 18 months NA b.

SIS Logic NA (a)

NA (Initiation, Actuation,and low pressure block auto reset) c.

CHP Signal SIS initiation NA 18 months NA

~

(5P Relay Output) d.

Pressurizer Pressure 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

l Instrument Channels 2.

Recirculation Actuation Sianal (RAS) a.

Manual Initiation NA 18 months NA b.

RAS Logic NA 18 months

NA l

c.

SIRWT Level Switches NA 18 months

18 months

l 3.

Auxiliary Feedwater Actuation Sianal (AFAS) a.

Manual Initiation NA 18 months NA b.

AFAS Logic NA 92 days NA c.

"A" SG Level 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

l d.

"B" SG Level 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

l 4.

Emeraency Power Seauencers a.

DBA Sequencer NA 92 days 18 months b.

Normal Shutdown Sequencer NA 18 Months 18 months (a) Test normal and emergency power functions using test circuits each 92 days.

Verify all automatic actuations and automatic resetting of low pressure block each 18 months.

For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12.

Amendment No. M B, 164 4-77

4.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.3 Instrumentation Surveillance Reauirements for Isolation Functions i

CHANNEL CHANNEL FUNCTIONAL CHANNEL Functional Unit CHECK TEST CALIBRATION

1. Containment Hiah Prg'

.1 (CHP)

a. CHP logic Trains NA 18 months NA

b. Containment Pressure NA 31 days 18 months Switches - Left Train

c. Containment Pressure NA 31 days 18 months Switches - Right Train t

2. Containment Hiah Radiation (CHR)

a. Manual Initiation NA 18 months NA

b. CHR Logic Trains NA 18 months NA l

c. Containment Area 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

Radiation Monitors

3. Steam Generator low Pressure (SGLP) j

a. Manual Actuation NA 18 months NA

b. SGLP Logic Trains NA 18 months NA l

c. "A" Steam Generator 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

Pressure

{

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d. "B" Steam Generator 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

Pressure

4. Enaineered Safeauards Pur.n Room Hiah Radiation a.

East Room Monitor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days la months b.

West Room Monitor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12.

Amendment No. MB,164 4-78

4.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.4 Instrumentation St rveillance Reauirements for Accic ent Monitorina CHANNEL CHANNEL Instrument CHECK CALIBRATION 1.

Wide Range Ts 31 days 18 months 2.

Wide Range Tc 31 days 18 months 3.

Wide Range Flux 31 days 18 months 4.

Containment Floor Water Level 31 days 18 months 5.

Subcooled Margin Monitor 31 days 18 months

l 6.

Wide Range Pressurizer Leve'l 31 days 18 months 7.

Containment H, Concentration 31 days 18 months 8.

Condensate Storage Tank Level 31 days 18 months 9.

Wide Range Pressurizer Pressure 31 days 18 months

l

10. Wide Range. Containment Pressure 31 days 18 months

11. Wide Range "A" SG Level 31 days 18 months

l

12. Wide Range "8" SG Level 31 days 18 months

l

13. Narrow Range "A" SG Pressure 31 days 18 months

l

14. Narrow Range "B" SG Pressure 31 days 18 months

l 15.

Position Indication for each 31 days 18 months Containment Isolation Valve

16. Core Exit Thermocouples (CET) 31 days 18 months'"'

Quadrant 1

17. Core Exit Thermocouples (CET) 31 days 18 months'"'

Quadrant 2

18. Core Exit Thermocouples (CET) 31 days 18 months'"'

Quadrant 3

19. Core Exit Thermocouples (CET) 31 days 18 months'"'

Quadrant 4

20. Reactor Vessel Water Level (RVWL) 31 days 18 months

21. High Range Containment Radiation 31 days 18 months

l (a) Calibrate by substituting a known voltage for thermocouple.

For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12.

Amendment No. MB, 164 4-79

4.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.5 I,nstrumenta", ion Surveillance Reouirements for A' ternate Shutdown Sys':em CHANNEL i

CHANNEL Instrument or Control CHECK

' FUNCTIONAL CHANNEL TEST CALIBRATION 1.

Start-up Range Flux (a)

(a) 18 months l 2.

Pressurizer Pressure 92 days NA 18 months

3.

Pressurizer Level 92 days NA 18 months 4.

1 Hot Leg Temperature 92 days NA 18 months 5.

2 Hot Leg Temperature 92 days NA 18 months 6.

1 Cold Leg Temperature 92 days NA 18 months 7.

2 Cold Leg Temperature 92 days-NA 18 months i

l 8.

"A" SG Pressure 92 days NA 18 months

l 9.

"B" SG Pressure 92 days NA 18 months

l l 10.

"A" SG Level 92 days NA 18 months

l 11.

B" SG Level 92 days NA 18 months *

12. SIRW Tank Level 92 days NA 18 months

33. P-88 Flow to "A" SC 18 months 18 months 18 months 14.

P-8B Flow to "B" SG 18 months 18 months 18 months 15.

P-8B Low Suction Alarm NA 18 months 18 months 36.

P-8B Steam Valve Control NA 18 months NA

17. AFW Flow Centro 1 "A" SG NA 18 months NA

18. AFW Flow Control "B"

SG NA 18 months NA

19. Transfer Switches, C-150 NA 18 months NA

20. Transfer Switch, C-150A NA 18 months NA (a) Once within 7 days prior to each reactor startup.

For Cycle 11 cn1, this surveillance need not be performed until prior to startup for Cyc1 12.

[

Amendment No. M2, M6, M2,164 4-80

~4.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.6 Instrumentaticn Surveillance Reauirements for Ot ier Safety

unctions-CHANNEL CHANNEL FUNCTIONAL CHANNEL Instrument CHECK TEST CALIBRATION 1.

Neutron Flux Monitoring 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (a) 18 months u

2.

Rod Position Indication 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (b) 18 months 3.

SIRW Tank Temperature 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months NA 18 months t

4.

Main Feedwater Flow 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s-Not Required 18 months

l-5.

Main Feedwater Temp.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Not Required 18 months

l 6.

AFW Flow Indication 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 18 months 18 months 7.

PCS Leakage Detection:

a.

Sump Level 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 18 months 18 months b.

Atmos. Gas Monitor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 18 months 18 months c.

Humidity Monitor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 18 months 18 months

l d.

Air Cooler Condensate NA 18 months Not Required l

Flow Switch 8a.

Primary Safety Valve NA 18 months 18 months l

acoustical monitor 1

8b/ Safety Valve / PORV'*'

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 18 months 18 months 9a.

tallpipe temperature 9b.

PORV Acoustical Monitor NA 18 months 18 months 9c.

PORV Sten Position 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 18 months 18 months 10.

PORV Block Valve 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months NA.

18 months Position Indication (a) Once within 7 days prior to each reactor startup.

(b) Verification of Regulating Rod Withdrawal and Shutdown Rod Insertion interlocks OPERABILITY only, once within 92 days prior to each reactor startup AND once prior to startup after each refueling.

(c) The tailpipe temperature indicator is common to the safety valves and PORVs For Cycle 11 only, this surveillance need not be performed until prior' to startup for Cycle 12.

(continued)

Amendment No. MG,164 4-81

4.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.6 (continued)

Instrumentation Surveillance Reauirements for Other Safety runctions CHANNEL CHANNEL FUNCTIONAL CHANNEL Instrument CHECK TEST CALIBRATION

11. SWS Break Detector NA 18 months 18 months 12.

Flux - AT Comparator 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months 13.

Rod Group Sequence NA 18 months 18 months Control / Alarm 14.

BAT Low Level Alarm NA 18 months No' Required 15.

Excore Deviation Alarm NA 18 months 18 months

16. ASI Alarm NA 18 months 18 months l 17.

SDC Suction Interlocks NA 18 months

18 months

l 18.

PDIL Alarm NA 31 days'*

18 months 19.

Fuel Pool Rad Monitor 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 31 days 18 months

20. Containment Refueling 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 31 days 18 months Radiation Monitor l (d) Setpoint verification only.

For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12.

}

Amendment No. MB,164 4-82 i

.

ML20082M724

Text

Attachment:

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