ML20236X424
| ML20236X424 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/04/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236X426 | List: |
| References | |
| NUDOCS 8712090182 | |
| Download: ML20236X424 (11) | |
Text
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NUCLEAR REGULATORY COMMISSION 3
.j WASW NGTON, D. C. 20555
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MISSISSIPPI POWER & LIGHT COMPANY SYSTEM ENERGY RESOURCES, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET N0. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. NPF-29 1.
The Nuclear Regulatory Commission (the Comission) has found that A.
The application for amendment by System Energy Resources, Inc.,
(the licensee), dated July 6,1987, as superseded October 23, 1987, and as supplemented November 19, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8712090182 871204 I
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'Accordingly, the license _is amended by changes to the Technical Specifications, as indicated in the attachment'to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B; as revised through. Amendment No. 38, are hereby incorporated into this license. System Energy Resources, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k)
Elinor G.' Adensam, Director Project Directorate 11-1 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4,1987
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s ATTACHMENT TO LICENSE AMENDMENT NO. 38 l
FACILITY OPERATING LICENSE NO. NPF-29 l
DOCKET NO. 50-416-Replace the following pages of the Appendix "A" Technica1' Specifications with the. attached pages..The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf page(s) have been provided to maintain document completeness.
Remove
. Insert 3/4 4-27 3/4 4-27 3/4 5-6 3/4 5-6 3/4 7-1 3/4 7-1 3/4/ 7-2 3/4 7-2 3/4 9-17 3/4 9-17 (overleaf) 3/4 9-18 3/4 9-18 3/4 9-19 3/4 9-19 3/4 9-20 3/4 9-20 (overleaf) e i
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REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) l system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *'##
with each loop consisting of at least:
a.
One OPERABLE RHR heat exchanger.
APPLICABILITY:
OPERATIONAL CONDITION 4.
ACTION:
a.
With less than the above required RHR shutdown cooling mode loops OPERABLE,
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within one hour 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 /> thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.
b.
With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor
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reactor coolant temperature and pressure at least once per hour.
c.
The provisions of Specification 3.0.4 are not applicable.**
SURVEILLANCE REQUIREMENTS 4.4.9.2 At least one shutdown cooling mode loop o the residual heat removal system or alternate method shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for 0
surveillance testing provided the other loop is OPERABLE and in operation.
- The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided the other loop is OPERABLE.
- The shutdown cooling mode loop may be removed from operation during hydrostatic testing.
- This exception is applicable until startup from the second refueling outage.
GRAND GULF-UNIT 1 3/4 4-27 Amendment No. 38
EMERGENCY CORE COOLING SYSTEMS 3/4 5.2 ECCS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE:
a.
The low pressure core spray (LPCS) system with a flow path capable of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.
b.
Low pressure coolant injection (LPCI) subsystem "A" of the RHR system j
with a flow path capable of taking suction from the suppression pool upon being manually realigned and transferring the water to the reactor vessel.
c.
Low pressure coolant injection (LPCI) subsystem "B" of the RHR system with a flow path capable of taking suction from the suppression pool i
upon being manually realigned and transferring the water to the reactor vessel.
I d.
Low pressure coolant injection (LPCI) subsys. tem "C" of the RHR system with a flow path capable of taking suction from the suppression pool upon being manually realigned and transferring the water to the reactor vessel, e.
The high pressure core spray (HPCS) system with a flow path capable of taking suction from one of the following water sources and trans-ferring the water through the spray sparger to the reactor vessel:
1.
From the suppression pool, or 2.
When the suppression pool level is less than the limit or is drained, from the condensate storage tank containing at least 170,000 available gallons of water, equivalent to a level of 18 feet.
APPLICABILITY:
OPERATIONAL CONDITION 4 and 5*.
ACTION:
a.
With one of the above required subsystems / systems inoperable, restore at least two subsystems / systems 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 suspendalloperationsthathaveapotentialfordrainingthereac)or vessel.
The provisions of Specification 3.0.4 are not applicable l
b.
With both of the above required subsystems / systems inoperable, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel.
Restore at least one subsystem / system 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 establish SECONDARY CONTAINMENT INTEGRITY within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
xThe ECCS is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the upper containment fuel pool gates are removed, the spent fuel pool gates are removed, and water level is maintained within the limits of Specifications 3.9.8 and 3.9.9.
- This exception is applicable until startup from the second refueling outage.
l GRAND GULF-UNIT 1 3/4 5-6 Amendment No. 38
3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS STANDBY SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION l
3.7.1.1 Each of the following independent standby service water (SSW) system.
1 subsystems shall be OPERABLE with each subsystem comprised of:
a.
An OPFDABLE flow path capable of taking suction from the associated SSW cooling tower basin and transferring the water through the RHR heat exchangers and to associated plant equipment, as required, shall be OPERABLE as follows:
1.
In OPERATIONAL CONDITIONS 1, 2, and 3:
two subsystems; and 2.
In OPERATIONAL CONDITIONS 4, 5, and *:
the subsystems associated with the systems and components required to be OPERABLE by Specifications 3.4.9.2, 3.5.2, 3.8.1.2, 3.9.11.1 or 3.9.11.2.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and *.
ACTION:
a.
In OPERATIONAL CONDITION 1, 2 or 3:
I 1.
With one SSW subsystem inoperable, restore the inoperable sub-system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least H0T 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 />.
2.
With both SSW subsystems inoperable, 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 />.
b.
In OPERATIONAL CONDITION 3 or 4 with the SSW subsystem, which is asso-ciated wis an RHR loop required OPERABLE by Specification 3.4.9.1 or 3.4.9.2, 4.erab13 declare the associated RHR loop inoperable and J
take the ACTION required by Specification 3.4.9.1 or 3.4.9.2, as appli-cable.
The provisions of Specifica entryintoOPERATIONALCONDITION4} ion 3.0.4arenotapplicablefor c.
In OPERATIONAL CONDITION 4 or 5 with the SSW subsystem, which is asso-l I
ciated with an ECCS pump required OPERABLE by Specification '
inoperable, declare the associated ECCS pump inoperable ar, ake the ACTION required by Specification 3.5.2.
The provisions of Specifica-tion 3.0.4 are not applicable.
)
xWhen handling irradiated fuel in the primary or secondary containment.
Whenever both SSW subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.
- This exception is applicable until startup from the second refueling outage.
l GRAND LULF-UNIT 1 3/4 7-1 Amendment No. 38 1
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PLANT SYSTEMS LIMITING CONDITION FOR OPERATION ACTION: (Continued) d.
In OPERATIONAL CONDITION 5 with the SSW subsystem, which is associated with an RHR system required OPERABLE by Specification 3.9.11.1 or 3.9.11.2, inoperable, declare the associated RHR system inoperable and take the ACTION required by Specification 3.9.11.1 or 3.9.11.2, asapplicabje.
The provisions of Specification 3.0.4 are not applicable l
e.
In OPERATIONAL CONDITION *, with the SSW subsystem, which is associated with a diesel generci.or required OPERABLE by Specification 3.8.1.2, inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.2.
The provisions of Specification 3.0.3 are not applicable.
f.
In OPERATIONAL CONDITIONS 1, 2, 3, 4, or 5 with the SSW subsystem, which is associated with a diesel generator required OPERABLE by Specification 3.8.1.1 or 3.8.1.2, inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2 as applicable.
SURVEILLANCE REQUIREMENTS 4.7.1.1 At least the above required standby service water system subsystem (s) shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown by verifying that each automatic valve servicing safety related equipment actuates to its correct position on an actuation test signal.
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- This exception is applicable until startup from the second refueling outage.
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GRAND GULF-UNIT 1 3/4 7-2 Amendment No. 7E 38
f REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS 4.9.10.2.1 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the start of removal of control rods and/or control rod drive mechanisms from the core and/or reactor pressure vessel 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 /> thereafter until all control rods and control rod drive mechanisms are reinstalled and all control rods are inserted in the core, verify that:
a.
The reactor mode switch is OPERABLE and locked in the Shutdown position or in the Refuel position per Specification 3.9.1.
b.
The SRM channels are OPERABLE per Specification 3.9.2.
c.
The SHUTDOWN MARGIN requirements of Specification 3.1.1 are satisfied.
d.
All other control rods are either inserted or have the surrounding four fuel assemblies removed from the' core cell.
The four fuel assemblies surrounding each control rod and/or control e.
rod drive mechanism to be removed from the core and/or reactor vessel are removed from the core cell.
f.
All fuel loading operations are suspended unless all control rods are inserted in the core.
l 4.9.10.2.2 Following replacement of all control rods and/or control rod drive mechanisms removed in accordance with this specification, perform a functional test of the "one-rod-out" Refuel position interlock, if this function had been bypassed.
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GRAND GULF-UNIT 1 3/4 9-17 1
l REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode train of the residual heat removal (RHR) system shall be OPERABLE and in operation
- with at least:
a.
One OPERABLE RHR heat exchanger train.
APPLICABILITY:
OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is greater than or equal to 22 feet 8 inches above the ton of the reactor pressure vessel flange.
ACTION:
a.
With no RHR shutdown cooling mode train OPERABLE, within one hour 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 /> thereafter, demonstrate the OPERABILITY of at least one alternate method capable of decay heat removal.
Otherwise, suspend all operations involving an increase in the reactor decay heat load and establish SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, b.
With no RHR shutdown cooling mode train in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.
The provisions of Specification 3.0.4 are not applicable.#
l c.
SURVEILLANCE REQUIREMENTS 4.9.11.1 At least one shutdown cooling mode train of the residual heat removal system or alternate method shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period.
- This exception is applicable until startup from the second refueling outage.
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GRAND GULF-UNIT 1 3/4 9-18 Amendment No. 38
REFUELING OPERATIONS LOW WATER LEVEL
. LIMITING CONDITION FOR OPERATION 3.9.11.2 Two shutdown cooling mode trains of the residual heat removal (RHR)
. system shall be OPERABLE and at least one train shall be in operation,* with each train consisting of at least:
a.
One OPERABLE RHR heat exchanger train.
APPLICABILITY:
OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is less than 22 feet 8 inches above the top of the reactor pressure-vessel flange.
ACTION:
a.
With,less.than the above required shutdown cooling mode trains of the RHR system 0PERABLE, within one hour 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 /> thereafter, demonstrate the OPERABILITY of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode train, b.
With no RHR shutdown cooling mode train in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour, The provisions of Specification 3.0.4 are not applicable.#
l c.
SURVEILLANCE REQUIREMENTS 4.9.11.2 At least one shutdown cooling mode train of the residual heat removal system or alternate method shall be verified to be in operation and circulating reactor coolant 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 The shutdown cooling pump me be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period.
- This exception is applicable until startup from the second refueling outage.
l l
GP.AND GULF-UNIT 1 3/4 9-19 Amendment No. 38 i
REFUELING OPERATIONS 3/4.9.12 HORIZONTAL FUEL TRANSFER SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 The horizontal fuel transfer system (HFTS) may be in operation provided that; Room 1A525, Auxiliary Building, elevation 182'0", the room through a.
which the transfer system penetrates, is sealed.
b.
All interlocks with the refueling and fuel handling platforms are OPERABLE.
t All HFT5 primary carriage position indicators are OPERABLE.
c.
APPLICABILITY: OPERATIONAL CONDITION 4* and 5*.
i ACTION:
I With the requirements of the above specification not satisfied, suspend HFT5 operation with the HFTS at either the Spent Fuel Building pool or the Reactor Containment Building pool terminal point.
SURVEILLANCE REQUIREMENTS 4.9.12 Witnin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the operation of HFT5 and at least once per 7 days thereafter, verify that:
Room 1A525, Auxiliary Building, elevation 182'0", the room through a.
which the transfer system penetrates, is sealed.
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b.
All interlocks with the refueling and fuel handling platforms are l
All HFT5 primary carriage position indicators are OPERABLE.
1 c.
I When the reactor mode switch is in the Refuel position.
A l
l GRAND GULF-UNIT 1 3/4 9-20
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