ML20210A304
| ML20210A304 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/29/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210A248 | List: |
| References | |
| NUDOCS 8702060451 | |
| Download: ML20210A304 (22) | |
Text
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nk WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 1 TO FACILITY OPERATING LICENSE N0. DPR-21 NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION, UNIT N0. 1 DOCKET N0. 50-245
1.0 INTRODUCTION
By letters dated October 7 and 16, 1985, Northeast Nuclear Energy Company (NNECO or the licensee) requested amendments to their technical specifi-cations (TS) (Appendix A to Operating License No. DPR-21) for Millstone Nuclear Power Station, Unit No. 1 (Millstone 1). The October 7, 1985 proposed changes would:
(1) consolidate Specification 3.5.F.7 and 3.5.F.8 to eliminate redundancy with respect to work on control rod drive mechanisms, fuel movement and fuel replacement during refueling conditions; (2) eliminate water volume requirements for the spent fuel pool and the refueling cavity but retain water level depth requirements in measured units of feet; and, (3) modify Low Pressure Coolant Injection (LPCI)/ Core Spray requirements, with the reactor in REFUEL CONDITION and the refueling cavity flooded, to allow the LPCI/ Core Spray pump breakers to be racked out. The October 16, 1985 proposed changes would add definition for REFUEL CONDITION and clarify related sections affected by the new definition.
A Notice of Consideration of Issuance of Amendment to License and Proposed l
No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested actions were published in Federal Register, on November 20, 1985 (50 FR 47865/47866). No request for hearing and no public coments were received.
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8702060451 870129 PDR ADOCK 05000245 P
2.0 DISCUSSION AND EVALUATION The licensee states that proposed change (1), to consolidate Specifications 3.5.F.7 and 3.5.F.8, is administrative in nature and serves to eliminate some of the redundant wording in the existing TSs. These TSs specify conditions for work on control rod drive mechanisms, and for fuel move-ment and replacement during refueling outages. The proposed TS change consolidates into Specification 3.5.F.7 each of the non-redundant require-ments contained in the current TSs.
In addition, change (2) alters the existing required refueling cavity water capacity of at least 383,000 gallons to 33 feet (also at least 383,000 gallons based on the licensee's submittal) by cross reference to Specification 3.10.C.
This change allows direct monitoring of the same variable with the same limit, using control room instruments. Change (3) modifies LPCI/ Core Spray requirements to allow the operator to rack out pump breakers to prevent an inadvertent injection and possible drywell and refuel floor flooding during refueling, while maintaining the ability to return the LPCI/ Core Spray systems to full operability is less than 2 minutes by racking in the breakers.
The staff agrees that proposed changes (1) and (2) are administrative in nature and finds these changes acceptable.
Proposed change (3) to the LPCI/ Core Spray pumps is less restrictive than the existing TS, in that it would allow the 4160 volt supply breakers to be racked out during refueling.
This proposal is more conservative than BWR Standard Technical Specifications (STS) in which LPCI/ Core Spray systems are not required to be operable when the vessel head is removed and the refuel cavity is flooded. The staff finds this proposed change an improvement in overall plant safety since LPCI/ Core Spray systems can be quickly made available to perform their intended safety function and the change protects against faulty actuation that could result in refueling floor flooding. Therefore, the prcposed change (3) is acceptable.
The October 16, 1985 proposed changes define REFUEL CONDITION and clarify operability requirements of various systems during the shutdown and refuel conditions.
The licensee states that, for the possible positions of the mode-selector-switch, only the REFUEL CONDITION is not defined in the existing TSs. The SHUTDOWN CONDITION has been previously defined as all operable control rods fully inserted, the reactor mode switch in the shutdown position, and no core alterations being performed. The existing definition has two categories, H0T SHUTDOWN (Reactor Coolant System (RCS) greater than 212*F) and COLD SHUTDOWN (RCS less than 212 F, with the reactorvented). The proposed definition for the Refuel Condition is patterned after the definition of the COLD SHUTDOWN Condition.
It provides for a lower maximum allowable RCS temperature (200'F), the switch being in REFUEL the reactor vessel being vented, and all control rods fully inserted (or no more than one rod not fully inserted with the refueling interlocksoperable).
Incorporation of this definition will permit clarifying the operability requirements of many systems.
The staff finds this proposed change, defining REFUEL CONDITION and including an additional restriction (the lower RCS temperature of 200 F),
and the resultant inclusion of the term REFUEL CONDITION in variots requirements to ensure consistency throughout the TS, improves the TS and makes them more consistent with STS. Therefore, these proposed changes are acceptable. During a May 6, 1986 telephone conversation, the licensee representative agreed to a number of other minor editing changes to capitalize the operating modes for consistency with definitions.
These changes have been included in this amendment.
The current technical specification followed by the proposed technical specification is presented below:
(1) Current Technical Specification None l
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Proposed Technical Specification Change NN REFUEL CONDITION The reactor is in the REFUEL CONDITION when all of the following conditions are met:
1)
All control rods are fully inserted oj; the refuel interlocks are operable with no more than one rod not fully inserted.
2)
The reactor mode switch is in the refuel position.
3)
The reactor coolant temperature is 200*F.
4)
The reactor vessel is vented.
NOTE:
It is permissible to perform the Refuel Interlock Functional Check, and still be considered in the REFUEL CONDITION.
(2) Current Technical Specification 3.4 STANDBY LIQUID CONTROL SYSTEM Applicability:
Applies to the operating status of the standby liquid control system.
Objective:
To assure the availability of the standby liquid control system.
Specification:
A.
Normal Operation During periods when fuel is in the reactor, the liquid poison system shall be operable except when the reactor is in the cold shutdown condition and all control rods are fully inserted and Specification 3.3.A is met and except as noted in Specification 3.4.B below.
Proposed Technical Specification Change A.
Normal Operation During periods when fuel is in the reactor, the liquid poison system shall be operable except when the reactor is in the COLD SHUTDOWN or REFUEL CONDITION and Specification 3.3.A is met, except as noted in Specification 3.4.B below.
(3) Current Technical Specification 3.4.B Operation with Inoperable Components From and after the date that a redundant component is made or found to be inoperable, Specification 3.4.A shall be considered fulfilled, provided that:
1.
The component is returned to an operable condition within 7 days, or i
2.
A written report shall be submitted to the Atomic Energy Commission when the maintenance to restore the component to an operable condition will last longer than 7 days, i
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Proposed Technical Specification Change 1
2.
A written report shall be submitted to the Nuclear Regulatory Commission when the maintenance to restore the component to operable condition will last longer than 7 days.
(4) Current Technical Specification 3.5.A.6 If the requirements of 3.5. A cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l Proposed Technical Specification Change 3.5.A.6 If the requirements of 3.5.A cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(5) Current Technical Specification 3.5.B.6 If the requirement of 3.5.B cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the COLD SHUTDOWN condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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i Proposed Technical Specification Change 3.5 B.6 If the requirement of 3.5.B cannot be met, an orderly shutdown shall be initiated and the reactor shall be in l
the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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(6) Current Technical Specification 3.5.C.4 If the requirements of 3.5.C cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Proposed Technical Specification Change 3.5.C.4 If the requirements of 3.5.C cannot be met, an orderly shutdown shall be initiated and the reactor coolant temperature shall be less than 330'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(7) Current Technical Specification 3.5.0.3 If the requirements of 3.5.D cannot be met, an orderly reactor shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Proposed Technical Specification Change 3.5.D.3 If the requirement of 3.5.D cannot be met, an orderly shutdown shall be initiated and the reactor coolant temperature shall be less than 330'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(8) Current Technical Specification 3.5.E.3 If the requirements of 3.5.E cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Proposed Technical Specification Change 3.5.E.3 If the requirements of 3.5.E cannot be met, an orderly shutdown shall be initiated and the reactor coolant shall be less than 330*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(9) Current Technical Specification 3.5.F.4 If the requirements of 3.5.F.1 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I Proposed Technical Specification Change 3.5.F.4 If the requirements of 3.5.F.1 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in l
the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(10) Current Technical Specification
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CORE AND CONTAINMENT COOLING SYSTEMS 3.5.F.7.
When irradiated fuel is in the reactor vessel and the reactor is in the cold shutdown condition or refueling I
condition, a single control rod may be withdrawn and the drive mechanism removed if the following conditions are satisfied:
(a) Fuel removal and replacement will not be done without a full complement of control rods.
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(b) No work will be performed in the reactor vessel other than fuel sipping while a control rod drive housing is l
open.
(c) Either 1) both core spray systems,11) both low pressure coolant injection systems, or 111) one core spray system and one low pressure coolant injection system supplied by independent electrical power shall be operable.
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(d) With the torus drained, 1) the operable low pressure coolant injection systems / core spray system will be aligned with the condensate storage tank and the condensate storage tank suction valve V7-58 locked open, li) the condensate storage tank shall contain 2
at least 414,000 gallons of usable water and the refueling cavity shall contain at least 383,000 gallons of water.
1 (e) The minimum electrical power source requirements shall be the same as specified in paragraph 3.7.B.4.
8.
Except as specified in 3.5.F.7, when irradiated fuel is in the reactor vessel and the reactor is in the refuel condition, fuel removal and replacement may be done provided the following conditions are satisfied:
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(a) Either 1) both core spray systems,11) both low pressure coolant injection systems, or iii) one core l
spray and one low pressure coolant injection system supplied by independent electrical power shall be operable.
(b) Withthetorusdrained1)theoperablelowpressure coolant injection systems / core spray system will be aligned with the condensate storage tank and the condensate storage tank suction valve V7-58 locked open,11) The condensate storage tank shall contain at least 414,000 gallons of usable water and the refueling cavity shall contain at least 383,000 gallons of water.
(c) The minimum electrical power source requirement shall be the same as specified in paragraph 3.7.B.4.
.g.
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(d) No work is being done which has a potential for draining the vessel.
Proposed Technical Specification Change 3.5.F.7.
When irradiated fuel is in the reactor vessel and the reactor is in the REFUEL CONDITION, a single control rod may be withdrawn and the drive mechanism replaced or fuel removal and replacement may be conducted provided that the following conditions are satisfied:
(a) The reactor vessel head is removed.
(b) The cavity is flooded.
(c) The spent fuel pool gates are removed.
(d) Water level is maintained within the limits of specification 3.10.C.
(e) Either(i)bothcorespraysystems,(ii)bothlow pressurecoolantinjectionsystems,or(iii)onecore spray system and one low pressure coolant injection system, each combination being supplied by independent electrical power, shall be operable or available for operation with the respective 4160 volt supply breaker (s)rackedout.
(f) Withthetorusdrained(i)theECCSconfiguration required in 3.5.F.7(e) shall be aligned with the condensate storage tank and the condensate storage tanksuctionvalveV7-58lockedopen,(ii)the condensate storage tank shall contain at least 414,000 gallons of usable water.
(g) The minimum electrical power source requirement shall be the same as specified in paragraph 3.7.B.4.
(h) No work will be performed in the reactor vessel other than fuel sipping while a control rod drive housing is open.
(1) Fuel removal and replacement will not be done without a full complement of control rods.
(j) During fuel movement no work being done which has the potential for draining the vessel.
(11) Current Technical Specification 3.6.C.
Coolant Chemistry 1.a. (Paragraph 3)
When the reactor is in the STARTUP/ HOT STANDBY or RUN mode with the reactor coolant at any temperature or in the SHUTDOWN mode with the average reactor coolant temperature greater than 212'F, if the reactor coolant specific activity is greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 during any continuous period of tin.e longer than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or is greater than 4.0 microcuries per gram have the reactor in COLD SHUTDOWN mode with the average reactor coolant temperature less than 212*F in 24 hou'rs.
1.b.(Paragraph 2)
When the reactor is in the STARTUP/ HOT STANDBY or RUN mode with the reactor coolant at any temperature or in the SHUTDOWN mode with the average reactor coolant temperature greater than 212"F.
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if the reactor coolant specific activity is greater than 100/
microcuries per gram have the reactor in COLD SHUTDOWN mode with the average reactor coolant temperature less than 212*F in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Proposed Technical Specification Change 1.a.(Paragraph 3)
When the reactor is in the STARTUP/ HOT STANDBY or RUN mode with the reactor coolant at any temperature or in the SHUTDOWN mode with the average reactor coolant temperature greater than 212'F, if the reactor coolant specific activity is greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 during any continuous period of time longer than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or is greater than 4.0 microcuries per gram have the reactor in COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1.b. (Paragraph 2)
When the reactor is in the STARTUP/ HOT STANDBY or RUN mode with the reactor coolant at any temperature or in the SHUTDOWN mode with the average reactor coolant temperature greater than 212*F, if the reactor coolant specific activity is greater than 100/
microcuries per gram have the reactor in COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(12) Current Technical Specification 3.6.G.
Jet Pumps 1
1.
Whenever the reactor is in the STARTUP/ HOT STAND 8Y or RUN MODES, all jet pumps shall be intact and all operating pumps shall be operable.
If it is determined that a jet pump is inoperable, an orderly shutdown shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
The indicated core flow is the sum of the flow indi-cation from each of the twenty jet pumps.
If flow indication failure occurs for two or more jet pumps, immediate corrective action shall be taken.
If flow indication cannot be obtained for at least nineteen jet pumps, an orderly shutdown shall be initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the reactor shall be in a COLD SHUTDOWN condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.H Recirculation Pump Flow Mismatch 2.
If Specification 3.6.H.1 cannot be met, one recirculation pump shall be tripped. Operation with a single recirculation pump is permitted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the recirculation pump is sooner made operable.
If the pump cannot be made operable, the reactor shall be in the COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.I.
Snubbers 2.
During all modes of operation except Cold Shutdown and Refueling all snubbers shall be operable.
4.
If the requirements of 3.6.I.2 and 3.6.I.3 cannot be met, an orderly shutdown shall be initiated and the t
reactor shall be in the COLD SHUTDOWN condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
e 5.
If a snubber is determined to be inoperable while the reactor is in the SHUTDOWN or REFUELING mode the snubber shall be made operable or replaced prior to reactor startup.
Proposed Technical Specification Change 3.6.G.
1.
Whenever the reactor is in the STARTUP/ HOT STANDBY or RUN MODE, all jet pumps shall be intact and all operating jet pumps shall be operable.
If it is determined that a jet pump is inoperable, an orderly shutdown shall be initiated and the reactor shall be in the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
The indicated core flow is the sum of the flow indi-cation from each of the twenty jet pumps.
If flow indication failure occurs for two or more jet pumps, l
immediate corrective action shall be taken.
If flow indication cannot be obtained for at least nineteen l
jet pumps, an orderly shutdown shall be initiated
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within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the reactor shall be in the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, l
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9 3.6.H.
Recirculation pump Flow Mismatch 2.
If Specification 3.6.H.a cannot be met, one recircu-lation pump shall Le tripped. Operation with a single recirculation pump is permitted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the recirculation pump is sooner made operable.
If the pump cannot be made operable, the reactor shall be in the COLD SHUTDOWN ore REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.I.
Snubbers 2.
During all modes of operation except COLD SHUTDOWN and REFUEL CONDITION, all snubbers shall be operable.
4.
If the requirements of 3.6.1.2 and 3.6.1.3 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the COLD SHUTDOWN or REFUEL CONDITION within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
5.
If a snubber is determined to be inoperable while the reactor is in the SHUTDOWN or REFUEL CONDITION, the snubber shall be made operable or replaced prior to reactor startup.
(13) Current Technical Specification 3.7.A.1.e.
If the torus water level monitoring system is disabled and cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the level monitoring system is 'made operable.
3.7.A.2.c.
If the drywell to torus differential pressure monitoring system is disabled and cannot be restored in six (6) hours, an orderly shutdown shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the differential pressure monitoring system is made operable.
Proposed Technical Specification Change 3.7.A.1.e.
If the torus water level monitoring system is disabled and cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the level monitoring system is made operable.
3.7.A.2.c.
If the drywell to torus differential pressure monitoring system is disabled and cannot be restoredinsix(6) hours,anorderlyshutdown shall be initiated and the reactor shall be in COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the differential pressure monitoring system is made operable.
9 (14) Current Technical Specification 1
l 3.7.A.5.c.
If Specification 3.7.A.S.a or b cannot be met, the situation shall be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the reactor shall be placed in a cold shutdown condition within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4 3.7.A.7 If the specifications of 3.7.A cannot be met, initiate i
an orderly shutdown and have the reactor in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.7.C.1.a.
The reactor is in the cold shutdown condition and Specification 3.3.A is met. -
b.
The reactor water temperature is below 212 F and the reactor coolant system is vented.
c.
No activity is being performed which can reduce the shutdown margin below that specified in Specification 3.3.A.
d.
The fuel cask or irradiated fuel is not being moved within the reactor building.
3.7.D.
Primary Containment Isolation valves 1.
During reactor power operating conditions, all isolation valves listed in Table 3.7.1 and all instrument line flow check valves shall be operable except as specified in 3.7.D.2.
3.
If Specification 3.7.D cannot be met, initiate an orderly shutdown and have reactor in cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Proposed Technical Specification Changes 3.7.A.5.c.
If Specification 3.7.A.S.a or b cannot be met, the situation shall be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the reactor shall be placed in COLD SHUTDOWN or REFUEL CONDITION within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.7.A.7 If the specifications of 3.7.A cannot be met, initiate an orderly shutdown and have the reactor in a COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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3.7.C.I.a.
The reactor is in the COLD SHUTDOWN CONDITION and Specification 3.3.A is met.
b.
The fuel cask or irradiated fuel is not being moved within the reactor building.
3.7.D.
Primary Containment Isolation valves 1.
During reactor power operating conditions, all isolation valves listed in Table 3.7.1 and all instrument line flow check valves shall be OPERABLE except as specified in 3.7.D.2.
3.
If Specification 3.7.D cannot be met, initiate an orderly shutdown and have reactor in the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(15) Current Technical Specification 3.12.A.4.b.4.
If 3.a above cannot be fulfilled, place the reactor in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following twenty-four (24) hours.
Proposed Technical Specification Change 3.12.A.4.b.4.
If 3.a above cannot be fulfilled, place the reactor in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN or REFUEL CONDITION within the following twenty-four(24) hours.
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(16) Current Technical Specification Bases 3.5.F.
Emergency Cooling Availability The purpose of Specification F is to assure a minimum of core cooling equipment is available at all times.
If, for example, one core spray were out of service and the emergency power source which powered the opposite core spray were out of service, only two LPCI pumps would be available.
Likewise, if two LPCI pumps were out of service and two emergency service water pumps on the opposite side were also out of service, no containment cooling would be available.
It is during refueling outages that major maintenance is performed and during such time that low pressure core cooling systems may be out of service depending on the activities being performed.
Specification F allows removal of one CRD mechanism or fuel removal and replacement while the torus is in a drained condition without compromising core cooling capability. The specification establishes the minimum operable low pressure core cooling system, water inventories, electrical power supplies and other additional requirements that must exist to allow such activities such as CRD mechanism maintenance or fuel removal and replacement, to be performed in parallel with other major activities.
The available core cooling capability for a potential draining of the reactor vessel while this work is performed is based on an estimated drain rate and the maintained minimum volume of water, 383,000 gallons, in the refueling cavity to be supplied to the reactor vessel.
In addition, the available low pressure core cooling systems are lined up to the condensate storage tank which w
supplements the reactor cavity water with an additional 450,000 gallons of water.
Thus, with the torus drained, a volume of approximately 800,000 gallons of water will be maintained available to be supplied to the reactor vessel.
A potential draining of the reactor vessel would allow this water to enter into the torus and after approximately 270,000 gallons accumulated (needed to meet minimum NPSH requirements for the LPCI and/or CS pumps) the torus would be able to serve as a common suction header. This would allow a closed loop operation of the LPCI or CS pumps after a re-lineup of these systems to the torus rather than the condensate storage tank is made.
During the time the vessel is open and CRD maintenance or fuel removal and replacement is underway the electrical sources of power will be:
two onsite emergency power sources (gas turbine and a diesel generator) and one offsite power, or two sources of offsite power and one onsite emergency power source.
The single failure criterion is met by the utilization of two independent low pressure core cooling subsystems and the availability of the three independent power supplies at all times. With the worst single failure -- loss of transfer bus number 7 a redundant LPCI or CS subsystem would still be available for service.
Proposed Technical Specification Change 3.5.F.
Emergency Cooling Availability.
The purpose of Specification F is to assure a minimum of core cooling equipment is available at all times.
If, for example, one core spray system were out of service and the emergency power source which powered the opposite core spray system were out of service, only two LPCI pumps would be available. Likewise, if two LPCI pumps were out of service and two emergency service water pumps on the opposite side were also out of service, no containment cooling would be available.
It is during refueling outages that major maintenance is performed and during such time that the low pressure core cooling systems may be out of service depending on the activities being performed.
Specification F allows removal of one CR0 mechanism or fuel removal and replacement while the torus is in a drained condition without compromising core cooling capability. The specification establishes the minimum operable low pressure core cooling systems, water inventories, electrical power supplies and other additional requirements that must exist to allow such activities as CRD mechanism maintenance or fuel removal and replacement to be performed in parallel with other major activities. The available core cooling capability for a potential draining of the reactor vessel while this work is performed is based on an estimated drain rate and the maintained minimum water level in the refueling cavity to be supplied to the reactor.
3.0
SUMMARY
We have evaluated the proposed changes to technical specifications and conclude that they do not involve any physical change to the plant's safety-related structures, systems, or componer.ts.
Further, these changes do not increase the likelihood of a malfunction of safety'-related equipment, increase the consequence of an accident previously analyzed, or create the possibility of a malfunction different from those previously evaluated.
Therefore, as stated above, we find the licensee's requested changes are acceptable.
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4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in the installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
6.0 PRINCIPAL CONTRIBUTOR This Safety Evaluation was prepared by Monte Conner.
Dated: January 29, 1987