ML20238C447

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Proposed Tech Spec Pages 1-2,3/4 1-1,3/4 1-2,3/4 1-6, 3/4 3-4,3/4 9-3 & 3/4 9-7,changing Definition of & Footnotes Re Core Alteration
ML20238C447
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 09/04/1987
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20238C330 List:
References
NUDOCS 8709100115
Download: ML20238C447 (7)


Text

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DEFINITIONS CORE ALTERATION 1.7 CORE ALTERATI0N shall be the addition, removal, relocation or movement of fuel, sources, incore instruments or reactivity controls within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Normal moveme'.? nf the SRMs, IRMs, or TIPS in their driving system is not considered a CORE ALTERATION. Suspension of CORE ALTERATIONS shall not preclude completien of the movement of a component to a safe conservative position.

CRITICAL POWER RATIO 1.8 The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by application of the GEXL correlation to cause some point in the assembly to experience boiling tran-ition, divided by the actual assembly operating power.

DOSE EQUIVALENT I-131 1.9 DOSE EQUIVALENT I-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, 1-134, and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

E-AVERAGE DISINTEGRATION ENERGY 1.10 E shall be the average, weighted in proportion to the concentration of each radionuclides in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegration, in MeV, for isotopes, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME 1.11 The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS actuation set-point at the channel sensor until the ECCS equipment is capable of performing its safety function, i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc. Times shall include diesel generator starting and sequence loading delays where appli-cable. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME 1.12 The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME shall be that time interval to complete suppression of the electric are between the fully open contacts of the recirculation pump circuit breaker from initial movement of the associated:

a. Turbine stop valves, and
b. Turbine control valves.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

S110REHAM - UNIT 1 1-2 8709100115 070904 PDR ADOCK 05000322 P PDR

.O 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.1.1 The SHUTDOWN MARGIN shall be equal to or greater than:

a. 0.38% delta k/k with the highest worth rod analytically determined, or
b. 0.28% delta k/k with the highest worth rod determined by test.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5. .

ACTION:

I With the SHUTDOWN MARGIN less than specified:

a. In OPERATIONAL CONDITION 1 or 2, reestablish the required SHUTDOWN l MARGIN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or 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 />.
b. In OPERATIONAL CONDITION 3 or 4, immediately verify all insertable control rods to be inserted and suspend all activities that could reduce the SHUTDOWN MARGIN. In OPERATIONAL CONDITION 4, establish SECONDARY CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
c. In OPERATIONAL CONDITION 5, suspend CORE ALTERATIONS
  • and other activities that could reduce the SHUTDOWN MARGIN and insert all #

insertable control rods within I hour. Establish SECONDARY CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 1

1 4.1.1 The SHUTDOWN MARGIN shall be determined to be equal to or greater than specified at any time during the fuel cycle:

a. By measurement, prior to or during the first startup after each refueling.
b. By measurement, within 500 MWD /T prior to the core average exposure at which the predicted SHUTDOWN MARGIN, including uncertainties and calculation biases, is equal to the specified limit.
c. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after detection of a withdrawn control rod that is immovable, as a result of excessive friction or mechanical interference, or is untrippable, except that the above required SHUTDOWN MARGIN shall be verified acceptable with an increased al]ovance for the withdrawn worth of the immovable or untrippable control rod.
  • Except movement of special moveable detectors. l SHOREHAM - UNIT 1 3/4 1-1

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" REACTIVITY CONTROL SYSTEMS 3/4.1.2 REACTIVITY ANOMALIES LIMITING CONDITION FOR OPERATION 3.1.2 The reactivity equivalence of the difference between the actual R0D DENSITY and the predicted R0D DENSITY shall not-exceed 1% delta k/k.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

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, ACTION:

With the reactivity equivalence difference exceeding 1% delta k/k:

a. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> perform an analysis to determine and explain the cause of the reactivity difference; operation may continue if the difference is explained and corrected.
b. 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 />.

SURVEILLANCE REQUIREMENTS 4.1.2 The reactivity equivalence of the difference between the actual ROD DENSITY and the predicted ROD DENSITY shall be verified to be less than or equal i to 1% delta k/k:

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a. During the first startup folicwing CORE ALTERATIONS *, and )i
b. At least once per 31 effective full power days during POWER OPERATION.

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  • Except movement of control rods vith their normal drive system. l SH0REHAM - UNIT 1 3/4 1-2

l I- '* . ' REACTIVITY CONTROL SYSTEMS CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION i

l 3.1.3.2 The maximum scram insertion time of each control rod from the fully withdrawn position to notch position 5, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed 7.0 seconds.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

l- a. With the maximum scram insertion time of one or more control rods exceeding 7 seconds:

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1. Declare the control rod (s) with the slow insertion time inoperable, and
2. Perform the Surveillance Requirements of Specification 4.1.3.2.c.

at'least once per 60 days when operation is continued with three or more control rods with maximum scram insertion times in excess ,

of 7.0 seconds.

l 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 />.

b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.1.3.2 The maximum scram insertion time of the control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:

a. For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS
  • or after a reactor shutd wn that is greater than 120 days.
b. For specifically affected individual control rods following maintenance on or modification to the control rod or control rod drive system which a could affect the scram insertion time of those specific control rods.,

and

c. For at least 10% of the control rods, on a rotating basis, at least 4 once per 120 days of POWER OPERATION.

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  • Except movement of special moveable detectors or normal control rod movement.

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SHOREHAM - UNIT 1 3/4 1-6

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TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION STATEMENTS ACTION 1 -

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 />.

ACTION 2 - Verify all insertable control rods to be inserted in the core and lock t'te reactor mode switch in the Shutdown position within i hour.

ACTION 3 - Sur pend all cperations involving CORE ALTERATIONS,* and insert all i

insertable control rods within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

l ACTION 4 - 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 />.

ACTION 5 -

Be in STARTUP with the main steam line isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> er 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 />.

ACTION 6 -

Initiate a reduction in THERMAL POWER within 15 minutes and reduce turbine first stage pressure to 16109psig,**equivalentto THERMAL POWER less than 30% of RATED THERMAL POWER, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

ACTION 7 - Verify all insertable control rods to be inserted within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 8 - Lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 9 - Suspend all operations involving CORE ALTERATIONS,* and insert all insertable control rods and lock the reactor rods switch in the 9%TDOWN position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

  • Except movement of special moveable detectors or replacement of LPRM strings provided SRM instrumentation is OPERABLE per Specification 3.9.2.
    • Initial serpoint. Final setpoint to be determined during the startup test program.

SHORE: LAM - UNIT 3/4 3-4

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.e-1I REFUELING OPERATIONAL

'3/4.9.2 INSTRUMENTATION LIMITING'C0dDITION FOR OPERATION 3.9 2 At least 2 source range monitor * (SRM) channels shall be OPERABLE and .

u ainsertedi to the-normal operating level with:

a.- Continuous visual. indication in the' control. room,

b. One of the required fHui detectors locates in the quadrant where CORE AL1ERATIONS.ar: being' performed and the other required-SRM detector located in an adjacent quadrant, and
c. The " shorting links" removed from the RPS circuitry prior to and during the- time gny control rod is withdrawn and shutdown margin -

demonstrations are in progress. ,

' APPLICABILITY: OPERATIONAL CONDITION 5.

ACTION:

With the. requirements of,the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS ** and insert all insertable control rods._

SURVEILLANCE REQUIREMENTS __,

14.9.2- Each of the above required SRM channels shall be demonstrated OPERABLE by:

a. At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
1. Performance of a CHAN1iEL CHECK, 2.- Verifying the detectors are inserted to the normal operating level, and
3. During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and another is located-in an adjacent quadrant.

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  • The use of special movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits.
    • Except movement of special movable detectors. l
  1. Not required for control rods removed per Specification 3.9.10.1 and 3.9.10.2 SHOREHAM - Unit 1 3/4 9-3 f

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.' REFUELING OPERATIONS.

- 3/4.9.5' COMMUNICATIONS LIMITING CONDITION FOR OPERATION

-Direct communicationishall be maintained-between the control room and

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x3.9.5 refueling platform personnel.

~ APPLICABILITY: ' OPERATIONAL CONDITION 5, during CORE ALTERATIONS.*

L ACTION:

When direct communication between the control room and refueling platform personnel cannot be maintained, immediately suspend CORE ALTERATIONS.*

SURVEILLANCE REQUIREMENTS 4.9.5~ Direct communication between the control room and refueling platform personnel shall be demonstrated within.one hour prior to the-start of and at

. least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.*

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  • Except movement of e mtrol1 rods with their. normal- drive ' system. ( ]

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SHOREHAM - unit 1 3/4 9-7 4

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