ML20116A358

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Proposed Tech Specs 2.1, Safety Limits & 3.3.C, Scram Insertion Times
ML20116A358
Person / Time
Site: Pilgrim
Issue date: 10/23/1992
From:
BOSTON EDISON CO.
To:
Shared Package
ML20116A251 List:
References
NUDOCS 9210290335
Download: ML20116A358 (8)
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1 Attachment B - Proposed Technical Specification 4

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9210290335.921023' DR ADOCK:05000293 PDR-

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2.0 SAFETY LIMITS 2.1 SAFETY LIMITS 2.1.1 With the reactor steam dome pressure < 785 psig or core flow

< 10% of rated core flow:

, THERMAL POWER shall be 5 25% of RATED THERMAL POWER 2.1.2 With the reactor steam dome pressure 2 785 psig and core flov 210% of rated core flow:

MINIMUM CRITICAL POWER RATIO thall be 2 1.07. l 2.1.3 Whenever the reactor is in the cold shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be less than 12 inches above the top of the normal active fuel zone.

2.1.4 Reactor steam dc'e m 2ssure shall be 11325 psig at any time when irradi.i.a~ cel is present in the reactor vessel.

2.2 SAFETY LlillT VIOLATIrg With any Safet, limit not met the following actions shall be met:

2.2.1 Within cne hour notify the NRC Operations Center in accordance with 10CFR50.72-2.2.2 Within two hours:

A. Restore compliance with all Safety Limits, and B. Insert all insertable control rods.

2.2.3 The Station Director and Senior Vice President - Nuclear and the Nuclear Safety Review and Audit Committee (NSRAC) sha'l be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.2.4 A Licensee Event Report shall be prepared pursuant to 10CFR50.73. The Licensee Event Report shall be submitted to the Commission, the Operations Review Committee (ORC), the NSRAC and the Station Director and Senior Vice President -

Nuclear within 30 days of the violation.

2.2.5 Critical operation of tha unit shall not be resumed until authorized by the Commission.

Amendment No. 15, 27, 42, 72, 133 6 l

i ju&SES (continued) i

REACTOR The Safety Limit for the reactor- steam' dome pressure has been STEAM DONE selected such that it is at a pressure below which it can be PRESSURE shown that the integrity of the system is not endangered.

(2.1.4) The reactor pressure vessel _is designed tolSection III of the ASME Boiler and Pressure Vessel Code- (1965 Edition, including the January 1966 Addendum), which permits a maxir.um pressure transient of 110%, 1375 psig, of design pressure 1250 psig.

The Safety Limit of 1325 psig, as measured by the reactor steam dome pressure indicator, is equivalent to 1375 psig at the lowest elevation of the reactor coolant system. The reactor coolant system is designed to the USAS Nuclear Power Piping Code, Section 831.1.0 for the reactor recirculation piping, which permits a maximum pressure transient of 120% of design pressures of 1148 psig at 562 f for action piping and 1241 psig at 562 F for discharge piping. 1:a pressure Safety Limit is selected to be the lowest transient overpressure allowed by the applicable codes.

REFERENCES 1. " General Electric Standard Application for Reactor Fuel,"

NEDE-240ll-P-A (Applicable Amend nent specified in the CORE OPERATING LIMITS REPDRT).

2. General Electric Thermal Analysis _ Basis (GETAB): Data, Ccerelation and Design Applicati:,, General Electric Co.

BWR Systems Department, January 1977, NEDE-10958-PA and NED0-10958-A.

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Amendment No. 15, 135 -(Next page'is 26) 10 l 4

LIMITING CONDITION FOR ODEFATION SMBVEILLANCE RE00lkEMENI

( 3.3.C Scram Insertion Time 4.3.C- Scram insertion Time

'2. The average of the scram 2. Within each 120 days of insertion times for the three opsration, a minimum of 10%

fastest control rods of all of the control rod drives, groups of four control rods on a rotating basis, shall in a two by two array shall be scram iested as in be no greater than: 4.3.C.l. An evaluhtion shall be completed every

% Inserted Avg, Scram 120 days of operation to From fully Instation provide reasonable Withdrawn _ fjme Sec. assurance that proper parformance is being ,

10 .58 maintained.

30 1.35 50 2.12 90 3.71 ,

3. The maximum scram insertion time for 90% insertion of any operf.ile control rod shali not exceed 7.00 seconds.

D. Control Rod Accumulators D. Lontrol Rod Accumulators At all reactor operating Once a shift, check the status pressures, a rod accumulator of the pressure and level may be inoperable provided alarms for each accumulator, that no othar control rod in the nine-rea square array arou,4 this rod has a:

1. . aperable accumulator.
2. Directional control valve electrically disarmed while in a non-fully inserted position.
3. Scram insertion time greater than the maximum permissible insertion time.

If a control rod with an  ;

inoperable accumulator-is '

inserted " full-in" and its directional control valves are electrically disarmed, it shall not be considered to have an inoperable

accumulator.

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Revision 129 Amendment No. 651 -124 84

9 Attachment C - Markec' Up Copy of Existing Technical Specifications l

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2.0 SAFET) LIMITS l

0 4;{Elg-2,) SAFETY LIMITS 2.1.1 Hith the--rt3ctor steala dom ; essui. < 785 psig or core flow < 10% of rated ore fiv=.

THERHAL F0HER shall be 1 25% of RATED THERMAL POWER.

2.1.1 Hith the reactor steam dome pressure 1 785 psig and core flos > 10% of rated core flow:

t oT HIN1 HUM CRITICAL POWER RATIO shall be 2 4 2,1.3 Whenever the reactor is in the coid shutdown condition witn irradiated fuel in the ' reactor vessel, the water level shall not be less than '0 inches-above the top of the normal active fuel zone.

2.1.4 Reactor steam come pressure shall be 1 1325 psig at any time wnen irtaaiated fuel is present in the reactor vessel.

2.2 SAFETY LIMIT VIOLATION

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Hith any Safety Limit not met the following ac ions ,shall be_ met.

<;'T , 2.2.1 Hithin one Lour notify the NRC Operations Center in

?f,. ? accordance with 10CFR50.72.

r 2.2.2 Hithin two hours:

A. Restore compliance with all Safety Limits, and s B. Inserc all insertable control rods.

2.2.3 The Station Director and Se..ior Vice Presiden! - Nuclear and the Nuclear Safety Review and Audit Committee (NSRAC) shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.2.4 A Licensee Event Report shall be prepared pursuant to n 10CTR50.73. The licensee Event Report shall be submitted to the Commission, the Occrations . Review Committse (ORC),

-the NSRAC and the Station Direttcr and Senior Vice President - Nuclear within 30 days of the-violation.

2.2.5 Critical operation of the unit sha ' ot be resumed until authorized by the Commission t

Revision 146 Amendment No. 75, 27, 42, 72, 133 6

i EMIS (cantinued)  !

The Safety Limit for tne reactor steam come pressure has been h*) REACTOR STEAM COME selected such that it is at a pressure below which it can be PRESSURE snown that the integrity of the system is not endangered.

(2.1.4) The reactor pressure vessel is designed to Section III of the ASME Boiler and Pressure Vessel Code (1965 Edition, including the January 1966 Adcendum), which permits a maximum prer 'Jre transient of 110*, 1375 psig, of design prersure 1250 psig.

The Safety Limit of 1325 psig, as measured by the reactor steam dome pressure indicator, is equivalent to 1375 psig at the lowest elevation of toe reactor coolant system. The reactor coolant system is designeo to the USAS Nuclear Power Piping Code, Section 831.1.0 for the reactor recirculation piping, which permits a maximum pressure transient or 1207. of design pressures of 1148 psig at 56T F for suction piping and 1241 psig at 562*F for discLrge piping, The pressure Safety -

Limit is selected to be the lowest transient overpressure ,

allowed by the applicable codes.

REFERENCES  !. " General Electric Standard Application for Reactor fuel,"

NEDE-240ll P-A ( Applicable AmendmentJpecified in the CORE OPERATING LIMITS REPORT). ~

2. GeneralElectricThermalAnalysisBasis(GETAB): Da t e. ,

.s Correlation and Design Application, General Electric Co.

BWR Systems Department, A cca; 197a viEO R tSH=

[ 37 E p tss Co.p p Performa -- valuatio '

uracy, Genera 6 e' EI IC 4 can' EWR c, .

tems gpdnt , J ne ' 5 /37

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O. __ g J %_7 i <t 7 7 ' west- i ms s - P A  %.Q mo - t e ra - A . .

, . A s' Revision 145 Amendment No. 15, 133 (Next page is 25) 10

o p l LlMillHG_C9NDITION FCJLQ!T>tATION SURVElltihfLREQQIfqEdERT 3.3.C Scu m_In5_ertion Tiy2e 4.3.C Stram Insertion Time

2. The average of the scram 2. Hithin each 120 days of insertion times for the three operation, a minimum of 10*. of fastest control rods of all the control rod drives, on a gre"ps of four control rods in rotating basis, shall be scram a two by two array shall be no tested as in 4.3.C.I. An greater than: evaluation shall be completed every 120 days of operation to
1. Inserted Avg. Scram provide reasonable assurance from fully Insertion that proper performance is being BliMEAWJL 11MfLSAL. maintained. y 10 .58 30 1.35 50 2.12 90

@ 3.7/ -

3. The maximum scram insertion time for 901. insertion of any operable control rod shall not exceed 7.00 seconds.

D. Control Rod Actumullists D. Control Rod Accumulators l At all reactor operating Once a shift, check the status of pressures, a rod accumulator may the pressure and level alarms for be inoperable provided that no each accumulator.

M other (ontrol rod in the nine-rod square array around this rod has a:

1. Inoperable accumult. tor.
2. Directional contral valve electrically disarmed while in a non-fully inserted Sosition,
3. Scram insertien time greater than the maxi.num permissible i nsertiot, t i'ne .

If a control rod with an inoperable accumulator is inserted

" full-in" and its directional control W.lves are electrically disarmed, it shall not be considered to have an inoperable accumulator.

Revision 129 Amendment No. 65,424- 84 -

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