ML20008F042
| ML20008F042 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/27/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20008F038 | List: |
| References | |
| NUDOCS 8103120105 | |
| Download: ML20008F042 (6) | |
Text
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It'.llt D s T AT E s IJf JCl i AH lil Gill. A'i OllY COMMIMlON ru o um. ima, o. c.-m.
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o MAINE YAtiKEE ATOMIC POWER COMPANY D_0C_ RET NO. 50-309 MAINE YANKEE AT0f11C POWER STATION AMENDMENT T0_ FACILITY OPERATING LICENSE Amendment No. 53 License No. DPR-36 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Maine Yankee Atomic Power Company
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(the licensee) dated June 24, 1977, September 13, 1979 and October.6, 1979, comply with the standards and requirements of the Atomic Energy 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 applications, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assura..ce (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 qonducted in compliance 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 accordahce with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i
have been satisfied.
2.
Accordingly,.the license is amended by adding paragraph 2.B (6)(e) and by changes to the Technical Specifications as indicated in the attachment to this license amendment. Paragraph 2.8.(6)(b) of Facility Operating License No. OPR-36 is hereby amended and paragraph 2.8.(6)(c) is added to' read as follows:
(b) Technical Specifications The Technical Specification's contained in Appendices A and B, as revised through Athendment No. 53, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8103120 \\
2-i (e) Secondary llater Chemistry Monitoring The licensee shall maintain a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
This program shall include:
1 1.
Identification of a sampling schedule for the critical parameters j
and limits for these parameters; 2.
Identification of the procedures used to quantify parameters that have critical limits; 1
3.
Identification of process sampling points; i
4 Procedures for the recording and management of data; 5.
Procedures defining corrective actions for off limit chemistry conditions; and 6.
A procedure identifying the authority responsible for the interpretation of the data, and the sequence and timing of 3
administrative events _ required to initiate corrective action.
3.
This amendment is effective as of the date of its issuance.
8 FOR THE NUCLEAR REGULATORY COMMISSION llT 0s.
Robert A. Clark, Chief 4
Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical. Specifications Date of Issuance: February 27, 1981 i
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ATTACHMErlT TO LICErlSE AMEllDMEt.T t:0. 53 TO FACILITY OPERATIt4G LICENSE f;0. DPR-36 DOCKET t10. 50-309 Revise Appendix A as follows:
Remove Pages Insert Pages 3.4.3 3.4.3 3.14-1 3.14-1 4.1-11 4.1-11 m
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1 C.
HesMual lleat Renoval System t
j 1.
The residual heat removal system (RHRS) must be isolated whenever the reactor coolant system I
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pressure exceeds 600 psig or the temperature l
exceeds 450 F.
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.i D.
Low Temperature Overpressurization Protection 4
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- 1. a.
The power operated relief valves, aligned i
for the low pressure set point, and the RilR i
spring relief valves shall be operabic for RCS overpressure protection whenever the RCS i
is less than the minimum pressurization temperature and the RCS is not vented, b.
If the conditions of D.I.a are not met, the RCS shall be depressurized and vented within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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EXCEPTION: One power operated relief or RHR spring relief may be inoperable i
for 7 days.
2.
No more than one HPSI pumg may be energized at RCS temperature below 220 F.
EXCEPTION: A second HPSI pump may be energized for up to 5 minutes for the purpose of totating operating equipment.
i NOTE: Reactor Coolant Pumps may be started (or jogged) only if there is a steam bubble i
in the pressurizer with a maximum icvel of80%ortheSGfRCStemperaturedifferential is less than 100 F.
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3.4.3 Amendment No. 53 l
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3.1 !.
PRI.WY SYSTD1 IMr. AGE App),1c ah111 t v :
Applies to limiting operation of the plant under varying 1
rates and conditions of primary syste: Ica ka ge.
Cb h tive:
To specify primary plant operability with prirary system leakage.
Specification:
A.
When the reactor is above 2 power, two reactor coolant i
Icak detection systems of dif ferent operating principles shall be operating, with one of the two systems sensitive to radioactivity in the containment.
Exception 1
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The syster.s sensitive to radioactivity may be out of service for a period of up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided two other eeans of reactor coolant leakage detection are operable.
i B.
If reactor coolant system indicated leakage exceeds 1 gpm by any of the neans available an investigation as to source and saf ety ieplicatiens vill be initiated as soon as practicable but no later than within four hours.
C.
If reactor coolant systen leakage exceeds any of the Specifications 1 through 5 below the reactor vill be shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The reactor shall not be 2
restarted until tne leak is repaired or until the problem is otherwise corrected.
1.
Leakage into the reactor containment of any magnitude that may be an indication of a deterioration of primary system pressure boundary strength velds or material.
p.
2.
Leakage into the reactor containment in excess of 1 gpm through bolted. closures, valve packing, or other mechanical connections.
3.
Leakage in excess of 1 g;m that is unexplained or I
unaccounted for.
l 4.
Leakage in excess of 10 gpm to aerated or uncontained sys't ems.
i 5.
Total leakage through all steam generator tubes shall not exceed 1.0 gpa,.
i 3.14-1 Amendment No. 3S' 53 d
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P Table'4.1-3 (continued)
Channel Lescrittice Surveillance Function Frequency Surveillance Method I
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- 7.. Interlocks - Isclaticn Calibrate R
Apply known pressure to the Valves on Residual Heat pressure sensors.
[
hemoval Line.
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8.
Containment Pressure a.
Check S
a.
Verify pressure indication.
b.
Calibrate R
b.
Known pressure applied to sensor.
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l-9.
HilH llX Outlet Teeperature a.
Check S(3) a.-
Verity temperature indications, f
I when the system is in operation.
k b.
Calibrate R
Known resistance substitute for RTD.
1 t
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- 10. Pressurizer Power Operated '
a.
Calibrate R
Apply known pressure to the
[
l Helier - Low Pressure pressure sensor. Manual actuation l
Setpoint b.
Test R(5) or each POR to verify solenoid i
opera tion.
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' (!) !!ct required ur.less tte reactor is in the power operating condition.
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(2)
'ot required decir.g Slant startup and shutdown periods.
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(3) !:ct required unen p;En is in the cold shutdown condition.
I iri) IMst be perforced w:tr.in 30 days prior to attaining a pcwer cperating condition.
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(-)) Must be perforp.ed pr10r to cooldown below 2200F.
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i-i t\\mendment No. 10 53 I
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