ML20247R905

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Proposed Tech Specs,Deleting Refs to Conditions Permitted During Startup Testing Program
ML20247R905
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/25/1989
From:
Public Service Enterprise Group
To:
Shared Package
ML20247R902 List:
References
NUDOCS 8910020102
Download: ML20247R905 (18)
v • d • e


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l ATTACHMENT 2 HCGS LICENSE CHANGE REQUEST 89-11, NLR-N89129 l , POWER ASCENSION' PROGRAM UPDATES The.following Technical Specifications have been revised to reflect the' proposed. changes:

Technical Specification Pace Table 3.3.1-1 3/4 3-5 Table 3.3.2-2 3/4 3-22 through.

3/4 3-25 Table 3.3.4.2-1 3/4 3-47 Table 3.3.7.1-1 3/4 3-65 Specification 4.4.2.1 3/4 4-8 Specification 3.4.3.1.a 3/4 4-10 Specification 3.4.5.c.1 3/4 4 Specification 4.5.1.c 3/4 5-5

-Specification 3.10.2.d 3/4 10-2 Specification 3/4.10.4 3/4 10-4 Specification 3/4.10.5 3/4 10-5 Specification 4.10.7 3/4 10-8 1 Bases 3/4.10.4 and B 3/4 10-1 3/4.10.5 8910020102 890925 PDR P

ADOCK 05000354 PDC

,.:* e TABLE 3.3.1-1 (Continued) l REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS .

(a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance 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) This function shall be automatically bypassed when the reactor mode switch is in the Run position.

(c) Unless adequate shutdown margin has been demonstrated per Sp* e cifica-tion 3.1.1, the " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn".

(d) The non-coincident NMS reactor trip function logic is such that all channels go to both trip systems. Therefore, when the " shorting links" are removed, the Minimum OPERABLE Channels Per the Trip System are 4 APRMS, 6 IRMS and 2 SRMS.

(e) An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less thsn 14 LPRM inputs to an APRM channel.

(f) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specifice. tion 3.10.1.

(g). This function shall be automatically bypassed when the reactor mode switch is not in the Run position.

(h) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required. -

(i) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

159.7 PSIG g N (j) This function shallibe automatically bypassed when turbine first stage pressure is M 153.3 ;;i n equivalent to THERMAL POWER less than 30% of 135.7 psts] RATED THERMAE POWER. To allow for instrument accuracy, calibration, and

\ drift, a setpoint of g132.d p;i;;**] is used.

(k) Also actuates the EOC-RPT system.

h

  • Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

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TABLE 3.3.7.1-1 (Continued)

RADIt.fION MONITORING INSTRUMENTATION ACTION ACTION 71 -

a. With one of the required monitors inoperable, place the inoperable channel in the tripped condition within one hour; restore the inoperable channel to OPERABLE status within 7 days, or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of the control room emergency filtration system in the pressurization mode of operation.
b. With both of the required monitors inoperable, initiate and maintain operation of the control room emergency filtration system in the pressurization mode of operation within one hour.

ACTION 72 -

With the required monitor inoperable, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 73 -

With the required monitor inoperable, obtain and analyze at least one sam le of the moqitored parameter at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 74 - With the number of channels OPERABLE less than required by Minimum Channels OPERABLE requirement, release (s) via this pathway may continue for up to 30 days provided:

a. The offgas system is not bypassed, and
b. Grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

}--

d'R: diction 1:v:1 re: ding: ::y be t: ken :t th: L ::1 R: diction Prc :sser (LnP) t le::t One per 24 hour: in lieu of obt ining and sn:1y:ing gr b ::=ple:

et 1 ::t On:: per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; pricr-to 120 days af ter initi:1 fuel 10 d.

T HOPE CREEK 3/4 3-65

i. 4- .;-

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.2.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE with the setpoint verified to be 5 30% of full open noise level **

by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 3'1 days, and a
b. CHANNEL CALIBRATION at least once per 18 months *.

4.4.2.2 At least 1/2 of the safety relief valves shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 18 months, and they shall be rotated such that all 14 Jafety

-relief valves are removed, set pressure tested and reinstalled or-replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 40 months.

  • The provisions of Specification 4.0.4 are not applicable provided the Surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
    • Initial setting shall be in accordance with the manufacturer's recommendations.,S -

Adjustment to the valve full open noise level shall be accomplished 'durin; thel .

l:t:rtup t::t pre;r:r.]

1' .

AFTER THE IMITIAL NolSE TRACES HAVE BEEN ANALYi!ED.

HOPE CREEK 3/4 4-8

_ _ _ _ _ _ _ - __ - ._______-_________________D

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s-REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR ODERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

a. The drywell atmosphere gaseous radioactivity monitoring system,
b. .The drywell floor and equipment drain sump monitoring system,
c. The drywell air cooler condensate flow rate monitoring system,
d. The drywell pressure monitoring system, and
e. The drywell temperature monitoring system.

APPLICABILITY.: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With only four of the above required leakage detection systems OPERABLE, opera-tion may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the re-quired drywell atmosphere gaseous radioactivity monitoring system, the drywell pressure monitoring system, the drywell temperature monitoring system and/or the drywell air cooler condensate flow rate monitoring system is inoperable;

  • otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .

SURVEILLANCE REQUIREMENTS i 4.4.3.1 The reactor coolant system leakage detection systems shall be  !

demonstrated OPERABLE by:

a. Drywell atmosphere gaseous radioactivity monitoring system performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
b. The drywell pressure shall be monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the drywell temperature shall be monitored at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c. Erywell floor and equipment drain sump monitoring system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION TEST at least once per 18 months.
d. Drywell air coolers condensate flow rate monitoring system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
  1. N:t r: pir:d t: 5: OPEPf3LE prkr t: 150 day: Ofter hitial fu:11 0d.

I HOPE CREEK 3/4 4-10

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y REACTOR COOLANT-SYSTEM

'3/4.4.5 ' SPECIFIC ACTIVITY LIMITING CONDITION'FOR OPERATION 3.4.5- The specific activity of the primary coolant shall be limited to:

a. Less'than or' equal to 0.2 microcuries per gram DOSE EQUIVALENT I-131, and-
b. Less than or equal to 1004 microcuries per gram.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 and 4.

ACTION:

a. In OPERATIONAL CONDITIONS 1, 2 or 3 with the specific activity of the primary coolant;
1. Greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 but less than or equal to 4.0 microcuries per. gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 4.~0 microcuries per gram DOSE EQUIVALENT I-131, be in at least HOT SHUTDOWN with the main steam line isolation valves' closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2. Greaterthan100/5microcuriespergram,beinatleastHOT .

SHUTDOWN with the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. In OPERATIONAL CONDITIONS ~1, 2, 3 or 4, with the specific activity.

of the primary coolant greater than 0.2 dicrocuries per gram DOSE EQUIVALENT I-131~or' greater than 100 M microcuries per gram, perform the sampling and analysis requirements of Item 4a of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within its limit.

c. In OPERATIONAL CONDITION 1 or 2, with:
1. THERMAL P changed by more than 15% of RATED THERMAL POWER in ore hou , or
2. The off g s level, at the SJAE, increased by more than 10,000 microcuries per second in one hour during steady state operation at release rates less than 75,000 microcuries per second, or
3. The off gas level, at the SJAE, increased by more than 15% in one hour during steady state operation at release rates greater than 75,000 microcuries per second, perform the sampling and analysis requirements of Item 4b of Table 4.4.5-1 until the' specific activity of the primary coolant is restored to within its limit.

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Y 3/4 4-18 HOPE CREEK

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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2. For the HPCI system, verifying that: )

a) The system develops a flow of at least 5600 gpm against a test line pressure corresponding to a reactor vessel pressure of > 200 psig, when steam is being supplied to the turbine at 200 + 15, -0 psig.**

b) The suction is automatically transferred from the condensate storage tank to the suppression chamber on a condensate storage tank water level - low signal and on a suppression chamber - water level high signal.

3. Performing a CHANNEL CALIBRATION of the CSS, and LPCI system discharge line " keep filled" alarm instrumentation.
4. Performing a CHANNEL CALIBRATION of the CSS header AP instruments-tion and verifying the setpoint to be i the allowable value of 4.4 psid
5. Performing a CHANNEL CALIBRATION of the LPCI header AP instrumen-tation and verifying the setpoint to be 1 the allowable value of 1.0 psid.
d. For the ADS:
1. At least once per 31 days, performing a CHANNEL FUNCTIONAL TEST of the Primary Containment Instrument Gas System low-low pressure alarm system.

At least once per 18 months:

2.

a) Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.

b) Manually opening each ADS valve when the reactor steam dome pressure is greater.than or equal to 100 psig** and observing that either:

1) The control valve or bypass valve position responds accordingly, or
2) There is a corresponding change in the measured steam flow.

c) Performing a CHANNEL CALIBRATION of the Primary Containment Instrument Gas System low-low pressure alarm system and verifying an alarm setpoint of 85 + 2 psig on decreasing pressure.

    • The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test. p f?niti:100tpcint. " :1 :etpcint te be deter ined during th :t:rtup t :t

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-SPECIAL TEST EXCEPTIONS 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.10.2 The sequence constraints imposed on control rod groups by the rod worth minimizer (RWM) per Specification 3.1.4.1 and by the rod sequence control system (RSCS) per Specification 3.1.4.2 may be suspended by means of bypass switches for the following tests provided that control rod movement prescribed for this testing is verified by a second licensed operator or other technically '

qualified member of the unit technical staff present at the reactor console:

a. Shutdown margin demonstrations, Specification 4.1.1.
b. Control rod scram, Specification 4.1.3.2.
c. Control rod friction measurements. p_,
d. St: rte; T::t are;rr with th: THER"AL POMER ?::: th:r 20% :f RATra g i T"C"".AL "0":R.

/ s APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

With the requirements of the above specification not satisfied, verify that the RWM and/or the RSCS is OPERABLE per Specifications 3.1.4.1 and 3.1.4.2, respectively.

SURVEILLANCE REQUIREMENTS 4.10.2 When the sequence constraints imposed by the RSCS and/or RWM are bypassed, verify:

a. That movement of the control rods from 75% ROD DENSITY to the RSCS low power setpoint is limited to the approved control rod withdrawal sequence during scram and friction tests.
b. That movement of control rods during shutdown margin demonstra-tions is limited to the prescribed sequence per Specification 3.10.3.
c. Conformance with this specification and test procedures by a second licensed operator or other technically qualified member of the unit technical staff.

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SPECIAL TEST EXCEPTIONS 3/4.10.4 RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION 3.10.4 The requirements of Specifications 3.4.1.1 and 3.4.1.3 that recirculation loops be in operation with matched pump speed may be suspended for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the performance of:

a. PHYSICS TESTS, provided that THERMAL POWER does not exceed 5% of RATED THERMAL POWER, P P

[ b. The Starte; Test Dregrarl i'

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2, during PHYSICS TESTS.1:nd the]

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qf ACTION:

a. With the above specified time limit exceeded, insert all control rods. .
b. With the above specified THERMAL POWER limit exceeded during PHYSICS TESTS, immediately place the reactor mode switch in the Shutdown position.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The time during which the above specified requirement has been suspended shall be verified to be less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at least once per hour during PHYSICS TESTS.;:r.: th: St:rtup T::t Pr:gr::./ A '

N 4.10.4.2 THERMAL POWER shall be determined to be less than 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

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SPECIAL TEST EXCEPTIONS 3/4.10.5 OXYGEN CONCENTRATION ,

LIMITING CONDITION FOR OPERATION

'l)JGERTl r Y

0.5 The provisions of Specification I.6.6.2 may be suspended during the per ance of the Startup Test Program antil 6 months after initial critic ity.

APPLICABIL  : OPERATIONAL CONDITION 1.

ACTION With the requirements o he above speci fication not s sfied, be.in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUI ENTS -

4.10.5 he number of months since initi al criticality shall be verifie o be le han or equc1 to 6 months at least once per 31 days during the Startu est ogram.

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A SPECIAL TEST EXCEPTIONS SU."EILLANCE REQUIREMENTS (Continued)

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4.10.7. (Continued)

. The RPS " shorting links" are removed.

4. The reactor mode switch is locked in the REFUEL po ition.
b. Perfo ance of a CHANNEL FUNLTIONAL TEST within 24 h urs prior to the start d at least once per J days during CORE ALT ATIONS.
c. Verifying or at least one Siti channel that the .ount rate is at least 0.7 cps":

. 1. Immediate following tt e loading of t e first 16 fuel bundles. .

2. At least on per 12 hot rs thereaft r during CORE ALTERATIONS.

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4 4

[Providedsignal-to-noiseis>2. Otherwise, 3 cps.

Y HOPE CREEK 3/4 10-8 .

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3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY the period when open vessel tests are being performed du PHYSICS TESTS.

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM it is necessary to bypass the sequence restraints on control r  !

i-additional surveillance requirements ensure that the specifications on heat The generation rates and shutdown margin requirements are not exceeded period when these tests are being performed and that individual rod worths doduring the not s',xceed the values assumed in the safety analysis.

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS Performance of shutdown margin demonstrations during open vessel testing monitored additional requires restrictions in order to ensure that criticality is properly and controlled.

These additional restrictions are specified in this LCO.

3/4.10.4 RECIRCULATION LOOPS This special test exception permits reactor criticality under no flow conditions and is required to perform certain s*rt; r4 PHYSICS TESTS while at low THERMAL POWER 1evels.

A

' 3/4.10.5 OXYGEN CONCENTRATION WSERT the oxygen concentrat' on specifications is .A 1 to provide access testing phase of ta' n tial startup and r er b s esset. : =t* rogram r

3/4.10.6 TRAINING STARTUPS This special test exception permits training startups to be performed with J

the reactor vessel depressurized at low THERMAL POWER and temperature while l

controlling RCS temperature with one RHR subsystem aligned in the shutdown cooling made in order to minimize contaminated water discharge to the radioactive waste disposal system.

,3/4.10.7 SPECIAL INSTRLOIENTATION - INITIAL CORE LOADING The material originally contained in Bases Section 3/4.10.7. was deleted with the issuance of Amendment No.14. However, to maintain the historical reference to this section, Bases Section 3/4.10.7 is intentionally left blank.  !

HOPE Cf.EEK B 3/4 10-1 Amenhent No.14

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' INSERT FOR.TS 3/4.10.5 AND' BASES-3/4.10.7 L

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The material' originally- contained in this Technical Specification was deleted with the issuance of Amendment No. [PM to' insert appropriate Amendment.No.J.- However,'to maintain the historical reference.to~this. specification, this section has been

, intentionally left' blank.

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