ML20247G757
| ML20247G757 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/27/1989 |
| From: | Reeves E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247G762 | List: |
| References | |
| NUDOCS 8904040310 | |
| Download: ML20247G757 (11) | |
Text
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UNITED STAVES
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NUCLEAR REGULATORY C,OMMISSION 5[
Gj WASHINGTON, D. C. 20555 l
~n SYSTEMS ENERGY RESOURCES IliC., ET AL.
DOCKET N0. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-29 d
1.
The Nuclear Regulatory Commission (the Commission) has fcund that-A.
The application for amendment by System Energy Researces, Inc.,
(the licensee), dated September 23, 1988, as revised November 30, December 16 and 21, 1988 and, as supplemented February 6 and 23, March 6 and 8,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regul.ations 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 i
Commission; C.
There is reasonable assurance (1) 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 ecmpliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Speci#ications, as indicated in the attachment to this license amendment; and p ragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby amended to read as follows:
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, (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 59, 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 Edward A. Reeves, Acting Director Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Isttachment:
Changes to the Technical Specifications Date of Issuance:
March 27, 1989 i
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1 (2) Technical Specifications The Technical Specificatims contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 59, 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 ecce.
4A^Sc Edward A. Reeves, Acting Director Project Directorate 11-1 Division of Reactor Projects I/II
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Office of Nuclear Reactor Regulation
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Attachment:
Changes to the Technical Specifications Date of Issuance:
.iarch 27, 1989 l
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J ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE N0. NPF-29 DOCKET.NO. 50-416 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3
3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 3-62 3/4 3-62 3/4 8-48 3/4 8-48 3/4 4-27 3/4 4-27 3/4 9-18 3/4 9-18 3/49 3/4 9-19 l
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COLD SHUTDOWN LIMITING CONDITION FOR OPERATION l
3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR)
~
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 *'##
l with each loop consisting of at least:
a.
b.
One OPERABLE RHR heat exchanger.
APPLICABILITY:
OPERATIONAL CONDITION 4.
ACTION:
With less than the above required RHR shutdown cooling mode loops OPERABLE, a.
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 l
OPERABILITY of at least one alternate method *** capable of decay heat I
removal for each inoperable RHR shutdown cooling mode loop.
The provisions of Specification 3.0.4 are not applicable for entry into OPERATIONAL CONDITION 4 from 5.**
b.
With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.
I 1
i SURVEILLANCE REQUIREMENTS l
4.4.9.2 At least one shutdown cooling mode loop of 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 mede loop may be removed from operation during hydrostatic testing.
- This exception is applicable until startup from the third refueling outage.
- The alternate decay heat removal system (ADHRS) may be used as the alternate decay heat removal method for the third refueling outage only.
GRAND GULF-UNIT 1 3/4 4-27 Amendment No.fh7, 59 m.
.__._m___
__m___ _
____m_______.____d_a______
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m 4
TABLE 3.8.4.2-1 (Continued) l MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICE (CON-4 TINU0US) (ACCIDENT SYSTEM (5)
VALVE NUMBER CONDITIONS) (NO)
AFFECTED Q1E12F074A.
Continuous RHR System Q1E12F026A Continuous RHR System Q1E12F082A No RHR System Q1E12F0828 No RHR System 4
Q1E12F290A Continuous RHR System Q1E12F047A Continuous RHR System Q1E12F027A Continuous RHR System Q1E12F073A Continuous RHR System Q1E12F346 Continuous RHR System Q1E12F024A Continuous RHR System Q1E12F087A Continuous RHR System Q1E12F048A Continuous RHR System Q1E12F042A Continuous RHR System j
Q1E12F004A Continuous RHR System Q1E12F003A Continuous RHR System Q1E12F011A Continuouc RHR System Q1E12F053A Coatinuous RHR System Q1E12F037A Continuous RHR System Q1E12F028A Continuous RHR System j
Q1E12F064A Continuous RHR System Q1E12F066A Cont'inuous RH7 System l
Q1E12F2908 Continuous RHR System Q1E12F004C Continuous RHR. System Q1E12F021 Continuous RHR System Q1E12F064C Continuous RHR System Q1E12F042C Continuous RHR System Q1E12F0488 Continuous RHR System Q1E12F049 Continuous RHR System Q1E12F037B Continuous RHR System Q1E12F0538 Continuous RHR System Q1E12F074B Continuous RHR System Q1E12F042B Continuous RHR System Q1E12F064B Continuous RHR System Q1E12F096 Continuous RHR System Q1E12F094 Continuous RHR System Q1E12F006B Continuous RHR System Q1E12F0118 Continuous RHR System Q1E12F0528 Continuous RHR System Q1E12F047B Continuous RHR System Q1E12F027B Continuous RHR System Q1E12F004B Continuous RHR System Q1E12F0878 Continuous RHR System
)
Q1E12F003B Continuous RHR System Q1E12F026B Continuous RHR System Q1E12F02aB Continuous RHR System Q1E12F028B Continuous RHR System Q1E12F009 Continuous RHR System Q1E12F073B Continuous RHR System Q1E12F0668 Continuous RHR System l
GRAND GULF-UNIT 1 3/4 8-48 Amendment No.59
~
4 REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATfR 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 OPERAB'_E 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 top of the reactor pressure vessel flange.
ACTION:
With no RHR shutdown cooling mode train OPERABLE, within one hour and at a.
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 bf decay hea't removal.
Otherwise, suspend l-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 />.
I 1
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.#
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 oparation and circulating reactor coolant at least once per 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 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.
- The alternate decay heat removal system (ADHRS) may be used as the alternate decay heat removal method for the third refueling outage only.
GRAND GULF-UNIT 1 3/4 9-18 Amendment NosGS, 59 l
L__________________.____.________..____.__._.
REFUELING OPERATIONS LOW WATER LEVEL 4
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.
b.
One OPERABLE RHR heat exchanger train.
l l
APPLICABILITY:
OPERATIONAL CONDITION 5, when irradiated fuel is in the r'eactor vessel and the water level is less than 22 feet 8 inches above the top of the reactor pressure vessel flange.
ACTION:
With less than the above required shutdown cooling mode trains of the RHR a.
system 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 l
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 for entry intg c.
OPERATIONAL CONDITION 5 from 4 or lowering reactor cavity water level.
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 />.
x 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 third refueling outage.
- The alternate decay heat removal system (ADHRS) may be used as the alternate decay heat removal method for the third refueling outage only.
GRAND GULF-UNIT 1 3/4 9-19 Amendment No/3A 59
.