ML20098D649

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Proposed Changes to Spec 4.0.4 & Administrative Procedures for SRMs & IRMs
ML20098D649
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 05/19/1992
From:
Public Service Enterprise Group
To:
Shared Package
ML20098D647 List:
References
NUDOCS 9205290211
Download: ML20098D649 (10)
v • d • e


Text

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ATTACHMEt1T 2, REQUEST FOR LICENSE AMENDMENT EXCEPTION TO SPECIFICATION 4.0.4 FOR SRMS AND IFMS FACILITY OPERATING LICENSE NPF-57 IIOPE CREEK GENERATING STATION DOCKET NO. 50-354 l

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I 9205290211 920519 ADOCK 05000354-PDR P PDR-

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. TI.QJirLQAL SPECIf1 CATION PAGES WITH PEN AND Il1K CHANGES The following Technical Specification for Facili.y Operating Iicence No. NPF-57 are effected by )

this license amendment requests i~

l Tqg_hnical Specification P_a5LQ l

Definitions, Table le2 1-11 3.3.1 3/4 3-1 3.3.6 3/4 3-56 3.3.7.6 3/4 3-88 3.4.1.2 3/4 4-4 l

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TABLE 1.2 OPERATIONAL CONDITIOJJS ,

MODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature
2. STARTUP Startup/ Hot Standby Any temperature
3. HOT SHUTDOWN Shutdown #'*** > 200'F
4. COLD SHUTDOWN Shutdown #'##'*** 1 200 F
5. REFUELING
  • Shutdown or Refuel **'# 5 140*F

,o c de/ vel

  1. The reactor mcde switch may be placed in the Run 3 of Startup/ Hot Standby, \/

position to test the switch interlock functions and related instrumentation ovided that the contrrl rods are verified to remain fully inserted _ by a econd licensed operator or other technically qualified member. of the unit wechnical staff.

    1. The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Speci fication 3.9.10.1.
  • Fuel in the reactor vessel with the vessel head closura bolts less than

-fully tensioned or with the head removed.

    • See Specias Test Exceptions 3.10.1 and 3.10.3.
      • The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided t9-t the one-rod-out r :

interlock is OPERABLE.

l HOPE CREEK 1-11 l: . -

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r - -u.= .-a-.. , u,n a-- . +- ns .a +."1-~w--a2..-u.u~ un--+--= a. ->> <-aanw ->.2 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITINGCONDE10NFOROPERATION 3.3.1 As a sinia'um, the reactor orotection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTI0N:

a. With the number of OPERABLE channels less than required by the Minimuu OPERABLE Channels per Trip Syster, requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condi-tion
  • within twelve hours. The provisions of Specification 3.0.4 are not l applicable,
b. With the number f GPERABLE channels less than required by tne Minimum OPERABLE Channels per Trio System requirement for both trip systems, place at least one trip system *" in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reacto protection system instrumentation channel shall be demonst ated OPcRABLE by the parformance of the CHAuNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.

4. 3.1. 2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at lust once per 18 months.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of tach reactor trip r> functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its.

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HOPE CREEK 3/4 3-56

1RR-N92068 HOPE CREEK IIR 92-02 Il[EERT FOR PAGE 3/4 3- M i i The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 from OPERATIONAL i CONDITION 1 for the Source Range lionitors or the Intermediato Range Monitors.

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'NST!!UMENTATION

_ SOURCE RANGE HONITORS LIMITING CONDITION FOR OPERATION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE:

a. In OPERATIONAL CCMDITION 2*, three.
o. In OPERATIONAL CONDITION 3 and 4, two.

,ADPLICABILITY: OPERATIONAL CONDITIONS 2*, 3 and 4 ACTION:

a. In OPERATIONAL CONDITION 2a with one of the acove required sou ce range monitor cnannels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or De in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
b. In OPERATIONAt. CONDITION 3 or 4 with one or more of the above-required source range monitor channels inoperable, verify all insertable control rodr te be inserted in the core and lock the reactor mode switch iis the Shutdown position within one hour.

SURVEILLANCE REOUIREMEN,TS_

0 3.7.6 Each of the above required source range monitor channels shsil be cemonstrat u OPERABLE by:

3. Performance of a;
1. CHANNEL CHECK at least once per:

a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in CONDITION 2*, and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in CONDITION 3 or 4.

2. CHANNEL CALIBRATION ** at least once per 18 months.
c. Performance of a CHANNEL FUNCTIONAL TEST:
1. Within 24 hot.rs prior to moving the reactor mode switen f rom I

the Shutdown position, if not performed within the previous .

j 7 days, and 4 [ y /f 2. At least once per 31 days.

) p 9)e#, /f c /eri fying, prior to oi hdrawal of control rods, tnat tne SRM 00vnt rate is at least 3 cp> with the oetector fully inserted. I

( } y / '/ 'Witn IRM's on range 2 or below.

( Q ,.. f " Neutron detectors may be excluoed f rom CHANNEL CALIBRATION.

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VJ HOPE CREEK 3/4 3-38 Amendment No. 31 y

NIR-N92068 IlOPE CREEK ICR 92-02 INSERT FOR PAGE 3/4 3-88

.d. The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2* or 3 from OPERATIONAL _ CONDITION 1. l l

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REACTOR COOLANT SYSTEM

{TPUMPS LIMITING CONDITION FOR OPERATION l

3. 4.1. 2 All jet pumps snall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

With one or more jet pumps inoperable, 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 />.

SURVEILLANCE REQUIREMENTS * '

4.4.1.2 All jet pumps shall be demonstrated OPERABLE as follows:

i a.

Each of the above required jet pumps shall be demonstrated OPERABLE prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by determining recirculation loop flow. total core flow and diffuser-to-lower plenum differential pressure for each jet pump and verifying that no two of the following conditions occur when the recirculation pumps are operating in accordance with Speci fication 3.4.1,3.

1.

The indicated recirculation loop flow differs by more than 10% l Trom the established pump speed-loop flou characteristics.

2.

The indicated total core flow differs by more than 10% from the

  • l established total core flow value derived from recirculation loop flow measurements.

3.

The indicated diffuser-to-lower plenum differential pressure of l any individual jet pump differs from the established patterns by core than 10%. l b.

During single recirculation loop operation, each of the above required jet pumps shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that no two of the following conditions occur:

1.

The indicated recirculation loop flow in the operating loop dif-fers by more than 10% from the established

  • pump speed-locp flow characteristics.

2.

The indicated total core flow differs by more t.han 10% from the established

  • total core flow value derived from. single p/f[v5e e rec kcula ogloopflowmpasurements.

3.

The indicated [,differe,nfekto-lower plenum dif ferential pressure

.of any individual jet pump differs from esteblished* single recirculation loop patterns by more than 10%.

c.

The orovisions of Specification 4.0.4 ye not applicable provided that this serveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 25% of RATED THERMAL POWER.

"During startup follcwing any refueling outage and in order to obtain single loop or two loop operation baseline data, data shall be recorded for the parameters listed to provide a basis for establishing the specified relationships. Com-parisons of the actual data in accordance with the criteria listed uall commence upon conclusion of the baseline data analysis. l l HOPE CREGA 3/4 4-4 l Amendment No. 3

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