ML20136D677
| ML20136D677 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/07/1997 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20136D681 | List: |
| References | |
| GL-90-006, NPF-06-A-180 NUDOCS 9703120458 | |
| Download: ML20136D677 (6) | |
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4 UNITED STATES j
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4 001 o%,*****/
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.180 License No. NPF-6 i
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1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application foi amendment by Entergy Operations, Inc. (the licensee) dated April 11, 1996 as supplemented by letters dated June 18, and September 5,1996, complies with the standards and requirements of the Atoaic Energy Act of 1954, as amended (the i
Act), and the Comission's rules and regulations set forth in i
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 Comission; i
C.
There ic 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 l
conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the i
comon defense and security or to the health and safety of the i
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.
9703120458 970307 PDR ADOCK 05000368 P
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1 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-6 is hereby amended to read as follows:
l 2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.180, are hereby incorporated in the license.
l The licensee shall operate the facility in accordance with the l
1echnical Specifications.
l 3.
The license amendment is effective within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION yl 0
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George Kalman, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 7, 1997 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 180 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise 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 PAGES INSERT PAGES 3/4 4-28 3/4 4-29 i
B 3/4 4-12 I
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mEAcrom co0LAnt arsTEx l
OVERPRESSURE PROTECTION
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LIMITING CONDITION POR OPERATION Low temperature overpressure protection (LTOP) shall be OPERABLE i
3.4.12 with each SIT Leolated*, ands 4,
Two LTOP relief valves with a lift setting of'5430 peig, or s.
The Reactor coolant System depressurised with an RCs vent path b.
l 26.38 square inches, t
SIT isolation is only required when SIT pressure is greater than or equal to Rcs pressure.
APPLICABILITY: MODE 4 with TC 5220*F, MODE 5, MODE 6 with reactor vessel t
head in place.
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With one LTOP relief valve inoperable in MODE 4, restore the a.
inoperable valve to OPERABLE status within 7 days or depressurise and vent the RCs through a 26.38 square inch vent path within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
With one LTOP relief valve inoperable.in MODE 5 or 6, either (1) b.
restore the inoperable relief valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) complete depressurisation and venting of the RCs through a 26.38 square inch vent path within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
With both LTOP relief valves inoperable, depressurize and vent c.
the Ecs through a 26.38 square inch vent path within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
With a SIT not isolated, isolate the affected SIT within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
d.
If required action is not met, either:
(1) Depressurise the SIT to less than the RCs pressure within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (2) Increase cold leg temperature to greater than or equal to 220*F within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The provisions of specification 3.0.4 are not applicable.
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ARKANSAS - UNIT 2 3/4 4-28 Amendment No.180 t,
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SURVEILLANCE REQUIREMENTS 4.4.12.1 verify both eats of LTOP relief valve isolation valves are open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the LTOP relief valves are being used for overpressure protection.
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4.4.12.2 The Rcs vent path shall be verified to be open at least once per i
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ** when the vent path is being used for overpressure j
protection.
1 4.4.12.3 verify that each SIT is isolated, when required, once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l 4.4.12.4 No additional LTOP relief valve Surveillance Requirements other than those required by specification 4.0.5.
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- Except when the vent path is provided with a valve which is locked, oealed, or otherwise secured in the open position, then verify this valve is open at least once per 31 days.
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ARKANSAS - UNIT 2 3/4 4-29 Amendment No. 180 i
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maAc1CR ODO! ANT SYSTEM l
l Shsts 3/4.4.12 IaN TEMPERAT1FRE DVERPRESEURE PROTECTION SYSTEMS i
Low temperature overpressure protection (LTOP) of the RCs, including the reactor vessel, is provided by rad==dmat relief valves on the pressuriser j
which discharge from a single discharge header. Each LTOP relief valve ig a direct action, spring-loaded relief valve, with orifice area of 6.38 in and a lift setting of $430 poig, and is capable of mitigating the worst-ease design basis pressuriaation event. The LTOP design basis event is a simultaneous lajection cf two EPs! pasps and all three charging pumps to a
the water-colid RCs. The analyses assume that the safety injection tanka j
are either isolated or are depressurised.
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The LTOP syetas, in sembination with the BCS heatup and cooldown limitations of Leo 3.4.9.1 and ad= int =trative restrictions on RCP operation, provides assurance that the reactor vessel non-ductile fracture limits are not exceeded during the design basis event at low RCs j
temperatures. These non-ductile fracture limits are identified as LTOP l
pressure-temperature (F-T) limits, which were specifically developed to provide a basis for the LTOP system. These LTOP P-T limits, along with the i
LTOP enable temperature, were developed using guidance provided in ASME j
Code Section II, Division 1, code Case N-514 that mandates that *LTOP systems shall limit the maximum pressure in the vessel to 110% of the j
pressure determined to satisfy appendix G, paragraph G-2215 of Section II, i
Division 1".
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The enable temperature of the LTOP isolation valves is based on any RCs t
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cold leg temperature reaching 220*P (including a 20*P uncertainty).
Although each relief valve is capable of mitigating the design basis LTOP e m nt, both valves are required to be opened below the enable temperature to meet the single failure criterion of MRC Branch Technical Position RSB 2
l 5-2, unless an RCs vent path of 6.39 ia (equivalent relief valve orifice area) or larger is maintained.
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4 ARKhMSAs - UNIT 2 5 3/4 4-12 Amendment No.180 l
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