ML19343C989
| ML19343C989 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/27/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19343C986 | List: |
| References | |
| NUDOCS 8104090031 | |
| Download: ML19343C989 (7) | |
Text
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[o UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
.j WASMNGTON. D. C. 20666
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CONNECTICUT LIGHT AND POWER COMPANY I
TiiE HARTFORD ELECTRIC LIGHT COMPANY l
WESTERN MASSACHUSETTS ELECTRIC COMPANY j
NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 l
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 74 License No. DPR-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Connecticut Light and Power Company, The Hartford Electric Light Company, Western Massachu-setts Electric Company, and Northeast Nuclear Energy Company (the licensees) dated March 20, 1978, and February 26, 1981, 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 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 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 accordance with 10 CFR Part al of the Commission's regulations and all applicable requirements have been satisfied.
4 810.409003l*
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Provisional Operating License No.
DPR-21 is hereby amended to read as follows:
. I B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74, are hereby incorporated in the license. Northeast Nuclear Energy Company shall operate the facility in accordance with the Technical Specification:.
3.
This license amandment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Denn s M. crutchfiel.
1ef Operating Reactors Bra ch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 27,1981 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 74 PROVISIONAL OPERATING LICENSE NO. DPR-21 DOCKET N0. 50-245 Replace the following pages* of the Appendix A Technical Specifications with the enclosed pages. The revised pages contain the captioned amendment number and vertical lines indicating the area of change.
1 i
PAGES 3/4 7-8 3/4 7-15 1
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- 0verleaf pages 3/4 7-7 and'3/4 7-16 are also included.
1 LIMITING CONDITION FOR OPERATION SURVEILLANCE FZQUIREMENT (2) The allowable operational lea 6 rate, L o (43), which t
shall be met prior to resump-tion of power operation following a test (either as measured or following repairs and retest), shall not exceed 0.90 weight percent per 24 hnurs which equals
- 0. 75 L.
p c.
Corrective action for II'CLT:
If leak repairs are necessary to meet the alinwable operational lea 6 rate, the integrated leak rate tests need not be repeated provided local leakage measure-ments are conducted and the leak rate differences prior to and after repairs, when Corrected (O the test pressure and deducted frnm the integrated leak rate measurements, yield a leakage rate value r.ot in excess of the allow-able operational leak rate.
d.
Frequency for IPCLT:
After the initial preoperational leakage rate test, two integrated leak rate tests shall be performed at approximately equal intervals between the major shutdas.ns for inservice inspection conducted at-ten-year intervals.
in addition, an integrated leakage tate test Amendment No. 51 3/4 7-7 si;all be performed at the end of the ten-year interval, which may coincide with the inservice
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O LlHITING CONDITION IOR OPERATION SURVEILLANCE REQUIREMENT e.
Local Leak Rate Tests (LLRI)
(1) Primary containment testable pentrations and isolation valves shall be tested at a pressure of 43 psig except the main steam line isolatfor valves shall be tested at a pressure of 25 psig each operating cycle. Bolted double-gasketed seals shall be tested whenever the seal is closed af ter being opened and at least once during eacli operating cycle.
(2) Personnel air lock door seals shall be tested at a pressure of 43 psig at least once every 6 months.
If the airlock is opened when primary containment integrity is required during the interval between the above tests, the air lock door seals shall be tested at 10 psig within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the first of a series of opening.
f.
Acceptance criteria and corrective action for LLRT:
If the total leakage rates listed below are exceeded, repairs and retests shall be perforned to correct the condition.
(1)
(a) A combined leakage rate of fE 0.60 L for all penetrations p
and valves, except for main steam isolation valves, subject to Type B and C tests when pressurized to P.
p (b) Any one penetration or isolation valve except main steam isolatio9
. valves 51 Lto (43)-
Amendment No. p, y, 74 3/4 7-8
Amendment No. 74 TABLE 3.7.1 PR34ARY CONTAlHMENT ISOLATION Isolation Valve (Valve,)
Number of Power Group Identi fica tion Number Opera ted, Valves Maximum Action on Operating)
Initiating Inboard Outbaard Time (Sec Position Signal 1
Main Steam Line Isolation (MS-1A, 2A, 18, 28, 1C, 2C, 4
4 3<T<5 0
GC 10,20) 1 Main Steam Line Drain (MS-5)
1 35 C
SC 1
Main Steam Line Drain (MS-6) 1 35 C
SC 1
Recirculation loop Sample Line (SM-1, 2) 1 1
5 C
SC 1
Isolation Condenser Vent to Main Steam Line IC-6, 7) 2 5
0 GC 2
Drywell Floor Drain (SS-3, 4) 2 20 0
GC 2
Drywell Equipment Drain (SS-13,14) 2 20 0
GC 2
Drywell Vent (AC-7) 1 10 C
SC 2
Drywell Vent Relief (AC-9) 1 15 C
SC 2
Drywell and Suppression Chamber Vent from Reactor 1
10 C
SC Building (AC-8) 2 Drywell Vent to Standby Gas Treatment System (AC-10) 1 10 C
SC 2
Suppression Chamber Vent (AC-11 1
' 10 C
SC 2
Suppression Chamber Vent Relief (AC-12) 1 15 C
SC 2
Suppression Chamber Supply (AC-6) 1 10 C
SC 2
Drywell Supply (AC-5) 1 10 C
SC 2
Drywell and Suppression Chamber Supply (AC-4) 1 10 C
SC 3
Cleanup Demineralizer System (CU-2) 1 18 0
GC 3
Cleanup Demineralizer System (CU-2A) 1 18 C
SC l
3 Cleanup Demineralizer System (CU-3, 5, 28) 3 18 0
GC 3
Shutdown Cooling System (50-1) 1 48 C
SC 3
ShutdownCoolingSystemI;SD-2A,28,4A,40) 4 48 C
3 Shutdown Cooling System I,SD-5) 1 48 C
SC 3
Reactor Head Cooling Line (HS-4) 1 45 C
SC 4
Isolation Condenser Steam Supply (IC-1) 1 24 0
GC 4
Isolation Condenser Steam Supply (10-2) 1 24 0
GC 4
Isolation Condenser Condensate Return (IC-3) 1 19 0
GC 4
IsolationCondenserCondensateReturn(IC-4) 1 19 C
SC Feedwater Check Valves (FW-9A, IDA, 9B,108) 2 2
NA 0
Process ControlRodIlydraulicReturnCheckValves(301-95,98) 1 1
NA 0
Process Nkby i bonho bheck Sb7, 8) e I
1 NA Pr ces 3/4 7-15
TABLE 3.7.1 Key: 0 = Open C = Closed SC = Stays Closed GC = Goes Closed NA = Not Appitcable Note:
Isolation groupings are as follows:
GROUP 1: The valves in Group 1 are closed upon any one of the following conditions:
1.
Reactor low-low water level (This signal also ' trips the reactor recirculation pumps.)
2.
Main steam line high radiation.
3.
Main steam line high flow.
j 4.
Main steam line tunnel high temperature.
5 Main steam line low pressure.
7 GROUP 2: The actions in Group 2 are initiated by any one of the following conditions:
i 1.
Reactor low water level.
2.
High drywell pressure.
GROUP 3: Reactor low water level alone initiates the following:
1.
Cleanup demineralizer systed isolation.
2.
Shutdown cooling system isolation.
3.
Reactor head cooling isolation.
GROUP 4:
Isolation valves associated with the isolation condenser are closed upon indication of either high isolation condenser steam or condensate flow.
4 4
1 1
3/4 7-16 a
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