ML20134K436

Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A

ML20134K436
Person / Time
Site:	Pilgrim
Issue date:	11/07/1996
From:	BOSTON EDISON CO.
To:
Shared Package
ML20134K430	List: BECO-LTR-96-094, Discusses power-flow Stability Tech Specs Re Installation of BWROG Enhanced Option 1A ML20134K436
References
NUDOCS 9611190107
Download: ML20134K436 (4)

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NEDO-32339 Supplement 4 PILGRIM TECHNICAL SFECIFICATIONS

• 3.2 PbWER DIST(tlBUTION LIMITS 3.11 REACTOR FUEL ASSEMBLY D.

Power / Flow Relatenshio Durina Power Operation 3.2.5 Fracten of Core Boiling Boundary (FCBD)

The power / flow relationship shall not exceed the limiting values LCO 3.2.5 FCBB shall be s 1.0.

specified in Uw CORE OPERATING LIMITS REPORT.

APPLICABILITY: THERMAL POWER and core flow in the Restricted Region as specified in the COLR.

surveinance thaw hmning value for the power / flow relatonship is MODE 1 when RPS Function 2.b, APRM Flow being exceeded, action shall be initiated within 15 minutes to Biased Simulated Thermal Power-High, Allowable restore operation to within the prescribed hmits. if the power / flow Value is " Setup" as specified in the COLR.

relationship is not returned to within the presenbod hmits within two (2) hours, the reactor shall be brought to the Cold Shutdown ACTIONS condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action l CONDITION COMPLETION TNE l REQUIRED ACTION A.

FCB8 not within limit A.1 Restore FCBS to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4.11 REACTOR FUEL ASSEMBLY for reasons other within limit.

than unexpected loss D.

Power / Flow Relationshio Durina Power Operation of feedwater heeting or unexpected Compliance with the power / flow relationship in Section 3.11.D shall be determined daily duLing reactor operation.

B.

Gequired Action and B1 initiate action to exit immediately associated Completion the Restricted Region.

3.6.6.

Thermal-Hvdraulic.jtability Time of Condition A not met.

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Core thermal power shall not exceed 25% of rated thermal power NOTE without forced recirculation.

Required Action B.1 mediet gn, g;,

PILGRIM NUCLEAR POWER STATION hahjl Simulated Thermal Restricted Region PNPS CORE OPERATING LIMITS REPORT com ed n ed t en ble 'alue to 3.4 Power / Flow Relationshio) Durina Power Operation unexpected loss of non-Setup" value, a

feedwater heating or Refert Technical Si-cificuh 3.11.D unexpected reduction in core flow.

The power / flow relationship shall not exceed the limiting values shown on the Power / Flow Opeinting Map in Figure 3.41.

FCD8 not within limit due to en unexpected loss of feedwater heating or unexpected reduction in core flow.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR3.2.5.1 NOTE Not required to be performed until 15 minutes after entry into the Restricted Region if entry was the result of an unexpected transient.

Verify FCBB s 1.0.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND Once within 15 minutes following l

unexpected transient.

9611190107 961107 PDR ADOCK 05000293 P

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J NEDO-32339 Supplement 1 PILGRIM TECHNICAL SPECIFICATIONS e

'3.3 INSTRUMENTATION 3.3.1.1 ReeCtor Pr[dection System instrumentation

[ Note-There is no change to the LCO, Apphcotwhty. Survedience Requirements or Actens i

specmcenon of the Standard improved TechrncW Specencenons ]

- Update me Mowingin TeNo 3 3.1.1 - 1:

REACTOR PROTECTION SYSTEM INSTRUMENTATION

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APPlacAsta coNDmoN Moofsom REG.NRED REFERENCED omER -

CHAredELS FRoM sPECIFiED P*R TRIP REGARED SURVEILLAfCE ALLoWA8LE FUNCThoN CoNDmCNS SYSTEM ACTloN o t REGAREMDn a VALUE 2 Average Power Range Monaars i

b. Flow Smed 1

p)

G SR 3 31.1.1 (b) i Simuisted SR 3 31.1.2 Thermal Power..

5434444 Hgh SR 3.3116 SR 3.31.1.13 1

SR33119 SM S.L t.t.f t SR 3 31.1.14 SR 3 311.15 SR 3 311.17 SM 3.3 f.f f 8 to)()

Anowable Velve spected m COLN lRevowers Note Funcbon 2 b is not essaconted wrarr e Lanubne Syshem softmg Anowebte valuee k Functorr 2 b are derived tom essaconsed cperebng hmste reperend a the COLR The operebng hmits are based on Lkensed operekng domem es6ebhshed Ibr cycle spectfac fuel and core doeten cherectensbes]

1 SR 3 31.11 Perforrn CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Station Procedure 2.1.15 - Daily Log Test 810 "APRM Channel Check" Not requered to be unbl12 hours after APRM High Flux Heat Balance Once Every 3 Days Venfy the absoluto dfMorence between the everage 7 days j

powar range monitor (APRM) channets and the calculated power is 5 2% RTP [ptus any gam l

ediustment required by LCO 3 2.4. "Averego Power Range Momtor (APRM) Setpomts") whee operebng at

& 25% RTP, s44344.3-A4ust4he.shanneweenseemw eenrecedaew heys means.

PNPS TABLE 4.1.2 Calibration Test Minimum Frequency SR 3 3.1.14 Cohbreto the local power range monitors.

1 p

g exposure PNPS TABLE 4.1.1 Functional Test Minimum Frequency (3)

SR 3 31.19 Perform CHANNEL FUNCTIONAL TEST.

[92] days APRM Flow Bias Trip Output Relaya (4)

Evevy 3 Months SR 3 3.1.111 NOTEC PNPS TABLE 4.1.2 Calibration Test Minimum Frequency

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1. Neutron detectors ero excluded 184 days APRM High Flux Calibrate Flow Bias signal (1) Every 3 Months

2. For Function 2 e. not required to be performed Flow Bias Signal 1

when entenne MODE 2 from MODE 1 until12 l

hours after entering MODE 2.

3 For Function 2 b. the dmetal comoonente of the flow ggptrol tre reference cards are exchased.

Peiform CHANNEL CALIBRATION.

SR 3 3.1.1.14 Venfy the APRM Flow Biased Simulated Thermal

[18] months PNPS TABLE 4.1.2 Calibration Test Minimum Frequency Power - High time constant es 5 [7] seconds APRM High Flux Calibrate Flow Comparator At least once every Flow Bias signal and Flow Bias Network 18 Months SR S 31.1.15 Pwform LOGIC SYSTEM FUNCTIONAL TEST.

[18] months Response time testing same as LSFT SR 3.31.1.17 NOTES

1. Neutron detectors are excluded Notes for Table 4.1.2

2. For Funcbon 6"n" equals 4 channels for the 5.

Response time is not a part of the routine Instrument channel test, but will purpose of determmmg the the STAGGERED TEST BASIS Frequency be checked once per operating cycle.

. Venfy the RPS RESPONSE TIME is wnhm bmits

[16] months on a STAGOERED TEST BASIS SR S3.1118 Ad the flow card tnp reference card to conform to e

m7 (Reviewst's Note Upon complebon of the Enhanced reaching to a calibrated flow signal" is required along with the 3 month celibration Option kA Stabshty solubon this SR supercedes SR equihbnum 33.1.1.3) condibons of the flow biased signal.

followmg refueling outage

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NEDO-32339-A PILGRIM TECHNICAL SPECIFICATIONS 3.3

,1NSTRUhENTATION 3.3.1.3 Period 4msed Dolection System Instrumentation (PSOS)

LCO 311.3 One channel of PSOS instrumentation shen be OPERA 8LE..

blG Each OPERA 8LE channel of PSOS instrumentation shall not indicale High-High DR Alarm APPUCABluTY THERMAL POWEft and core flow in the Restnoted Region as specNied in the COLR.

THERMAL POWER and core flow in the Monitored Region as 3.11 REACTOR FUEL ASSEMBLY specWied in the COLR.

ACTIONS cr#OTION REOJtRED ACTION COMPLETION TIMfi g

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A. Any OPERA 8LE PSOS A.1 Place the reactor rnode Irnmediately specified in the CORE OPERATING LIMITS REPORT.

channel indicating switch in the shutdown HigMingh DR Alarm.

posMion B. Required PSDS channel 8.1 N'OTE If at an@ W p operk R k MMW h nonnel inoperable while in the only applicable if RPS surveillance that the hmiting value for the power / flow relationship is estrW Rege u

p being exceeded, action shall be initiated within 15 minutes to Thermal Power-Hegh, restore operation to within the presenbod limits. If the power / flow Vetue l*

relationship is not returned to within the prescribed tirnits within two (2) hours, the reactor shall be brought to the Cold Shutdown initiale action to exit the immediet*

condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action Restricted Region shall continue until reactor operation is within the prescribed limits.

8.2 Piece the reactor mode immdiately switch in the shutdown position C. Required PSOS channel C.1 Initiate action to exit the 15 minutes inoperable while in the Monitored Region Monitored Region SURVElLLANCE REQUIREMENTS q

SURVEILLANCE FREQUENCY S23.3.1.3.1 Verify each OPERABLE channel of PSOS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> instrumentalxwi not in High-High DR Alarm SR 3.3.1.3.2 Perform Channel Check 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.3.3 Perform Channel Functional 24 months

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NEDC-32339 Supplement 4 PILGRIM TECHNICAL SPECIFICATIONS I

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating

[ Reviewer's Note: The only change to the RCS section is the LCO for Recirculation Loops Operating. The unchanged sections are not repeated herein.]

LCO 3.4.1 Two recirculation loops with rnatched flows shall be in operation, FACILITY OPERATING LICENSE QB Docket No. 50.293 One recirculation loop may be in operation provided the E.

Tim reactor shall not be operated with one recirculation loop out of following limits are applied when the associated LCO is service for rnore than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the reactor operating, if one applicable:

recirculation loop is out of service, the plant shall be placed in the hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the loop is sooner a.

[no changeJ returned to service.

b.

[no change]

C.

LCO 3.3.1.1," Reactor Protection System (RPS)

Instrumentation, Function 2.b (Average Power Range Monitor Flow Biased Simulated Thermal Power-High)

Allowable Value for Single-loop operation as i

specified in the COLR

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