ML20082H061
| ML20082H061 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  (NPF-29-A-081, NPF-29-A-81) |
| Issue date: | 08/12/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082H064 | List: |
| References | |
| NUDOCS 9108230012 | |
| Download: ML20082H061 (7) | |
Text
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UNITED STATES 5I E
NUCLEAR REGULATORY COMMISSION o,
f WASHINoToN, D.C. 20066 ENTERGY OPERATIONS, INC.
SYSTEM ENERGY RESOURCES, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION MidSISSIPPI POWER AND LIGHT COMPANY DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 I
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. NPF-29 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc.. (the licensee) dated March 15, 1991, as revised May 24, 1991, complies with the standards and requirements of the Atomic Er.ergy Act of 1954, as amended (the Act), and the Commission'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 Commission's regulations; D.
The issuance of this amendment will not be inimical tc the common deferse 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.
9108230012 910012 PDR ADOCK 05000416 P
-. - -. 2.
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.81 are hereby incorporated into this license.
Entergy Operations, 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 sbu S
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Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V Office'of Nuclear Reactor Regulation Attechment:
Changes to the Technical Specifications Date of Issuance:
August 12, 1991 I
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ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. NPF-29 00CKEl 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.
The corresponding overleaf pages are also included to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 4-20 3/4 4-20 3/4 4-22 3/4 4-22 l
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REACTOR COOLANT SYSTEM 3/4.4.6 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDIT40N FOR OPERATION 3.4.6.1 The reactor coolant system pressure and reactor vessel metal tempera-ture shall be limited in accordance with the limit lines shown on Figure 3.4.6.1-1 (1) curve A for hydrostatic or leak testing; (2) curve 8 for heatup by non-nuclear means, cooldown following a nuclear shutdown and low power PHYSICS TESTS; and (3) curve C for operations with a critical core other than low power PHYSICS TESTS, with:
A maximum reactor coolant heatup of 100*F in any one hour period, a.
b.
A maximum reactor coolant cooldown of 100'F in any one hour period, A maximum temperature change of less than or equal to 10'F in any c.
one hour period during inservice hydrostat1c (7d leak testing operations above the heatup and cooldown limit curves, and The reactor vessel flange and head flange temperature greater thaa or d.
equal to 70'F when reactor vessel head bolting studs are under tension.
APPLICABILITY:
At all times.
ACTION:
With any of the above limits exceeded, restore the temperature and/or pressure to within the limits within 30 minuter; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system; determine that the reactor coolant system remains acceptable for continued operations or be in at least HOT SHUTOOWN.
within 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 />.
SURVEILLANCE REQUIREMENTS 4.4.6.1.1 During system heatup, cooldown and inservice leak and hydrostatic testing operations, the reactor coolant system temperature and pressure shall be determined to be within the above required heatup and cooldown limits and the reactor coolant system pressure and reactor vessel metal temperature shall be determined to be to the right of the limit lines of Figure 3.4.6.1-1 curves A or B, as applicable, at least once per 30 minutes.
l GRAND GULF-UNIT 1 3/4 4-19 Amendment No. 75
REACTOR COOLANT SYSTEM SUR'/EILLANCE REQUIREMENTS (Continued) 4.4.6.1.2 The reactor coolant system pressure and reactor vessel metal temperature shall be determined to be to the right of the criticality limit line of Figure 3.4.6.1-1 curve C within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality and at least once per 30 minutes during system heatup.
4.4.6.1.3 The reactor vessel flange and head flange temperature shall be verified to be greater than or equal to 70'F:
In OPERATIONAL CONDITION 4 when reactor coolant system temperature a.
is:
1.
5 100'F, at least once.per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
5 80'F, at least once per 30 minutes, b.
Within 30 minutes prior to and at least once per 30 minutes during tensioning of the reactor vessel head bolting studs.
4.4.6.1.4 The reactor vessel material specimens shall be removed and examined to determine changes in material properties as required by 10 CFR 50,-Appendix H.
I 4.4.6.1.5 The pressure-temperature limit curves in Figure 3.4.6.1-1 are valid j
through 10 effective full power years (EFPY) and shall be re-evaluated prior to exceeding 10EFPY.
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