ML19345F775
| ML19345F775 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/13/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345F771 | List: |
| References | |
| NUDOCS 8102190263 | |
| Download: ML19345F775 (9) | |
Text
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o UNITED STATES 3,, (
i NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20556 E
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CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated December 5,1980, as suppler.ented December 19, 1980, complies 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 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 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.
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8102180 U )
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amencment and paragraph 2.C(2) of Facility Operating License No. OPR-6 is hereby amended to read as follows:
(2) Technical Scecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 37, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CCMMISSION
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D"en'n'iY h. Crutenfi el d,,ief
".perating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 13, 1981
ATTACHMENT TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. OPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified belcw and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3-4 3-4 3-da 3-5 3-5*
11-14 11-14 11-15 11-15 11-16 11-16 i
- No changes were made to these pages. They were retyped for format purposes only.
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3.4.2 (Contd) possibility of excessive external pressure on the con-tainment sphere due to atmospheric changes, the two valves in the ventilation supply line snall be automatically opened wherever the differential pressure exceeds 1 psi, overriding all other signals. The valves shall reclose when the internal pressure is still slightly below atmos-pheric.
The 6 second inlet valve clnsure requirement in the first sentence of this paragraph is changes to be 10 seconds beginning with the issuance of this Change No. 42 and continuing for a period not to exceed six months thereafter.
3.4.3 Operating Requirements (a) Normally-open lines, carrying fluids out of the contain-ment sphere, shall be closed automatically upon a signal indicating high containment sphere pressure or low water level in the reactor vessel. These automatic isolation valves shall also close upon instrument air or power failure, and upon manual trip from the control room.
(b) Normally-open lines, carrying fluids into the contain-ment sphere, shall be equipped with check valves to prevent backflow upon loss of inward propellent force.
In addition, these lines shall be capable of being secured by manually operated gate valves or by air-operated control valves. The latter shall close upon air or power failure, with exception of the supply line to the control rod drive hydraulic system. Valves in this control rod hydraulic system line shall fail open to insure continuous water supply, and backup isolation shall be provided by integral valves in the control rod drive pumps.
(c) Closing times on mater-operated isolation valves shall be as follows:
Description Closing Time (Seconds)
Main Steam (M0 7050) 60 Main Steam Drain (M0 7065) 60 3.5 POST-INCIDENT SPRAY SYSTEM Containment effectiveness shall be supplemented by a contain-ment sphere post-incident spray system in the event of an accident involving loss of coolant from a primary system rupture.
Change Nc. 7, 7,
Amen men: No.
3-4
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3.5.1 Design Features Shall Be As Follows:
(a) Number of Sets of Spray No::les 2
(b) Capacity of Spray Sets at 100 Psid No::le Pressure (i)
Primary Spray Set, Gpm 146
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(ii) Secondary Spray Set, Gpm 233
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(c) System Actuation j.
(i)
Primary Spray Set Automatic D-C Operated (ii) Secondary Spray Set Remote Manual A-C Operated l
'i.
.l (d) Signal Used to Actuate High Containment Sphere Pressure 4
(e) Signal Trip Setting
< 2.2 Psig j
(f) Reserve Water Supply Lake Mir.higan i
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Amendment No. 37
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3.5.2 Ooerating Requirements (a) Deleted (b) Water aidition to the containment sphere must be manually stopped efore the accumulated water level reaches an ele-vation of 0 6 feet.
(c) Deleted 3.6 CONTAINMENT REQUIREMENTS Containment sphere integrity shall be maintained during power operation, refueling operation, shndown and cold shutdown condi-tions except as specified by a ststem of procedures and controls to be established for occcsi;ns when containment must be breached during cold shutdowr..
3.7 CONTAINMENT SPHERE LEAKAGE TESTING For the purpose of this specification, leakage rate is defined as the percent of the contained atmosphere (weight basis) which escapes per day (24 hrs) under the defined pressure conditions through any leaks in the containment boundary and all isolation I
valves and their associated piping.
The maximum allowable integrated leakage rate shall not exceed 0.5%/ day of the containment atmosphere (weight basis) at the design pressure of 27 psig. The procedure for containment sphere lede;e testing shall be:
(a) At least once every 6 months, the personnel lock, the equip-ment lock and the sphere supply-and-exhaust ventilation valves shall be pressurized, with air to 20 psig, to test their leak tight-Amendment No. M, 37 Change No. /, 26, 3-5
1.imiting Conditions for Operation Surveillance itequi rement 11.3.3.1 CorlTAINMENT SPRAY SYSTD4 11.1.3.1 6
6 CONTAINMENT SPilAY SYSTEM
_Arplicability:
Applicability:
Applica to the operating status of the con-Applies to the testing of the containsment tainment spray system.
apray system.
Objective:
Oh,}ec t i ve :
To us.sure the capability of the containstent To' veri fy the operability of the containment spray system to reduce containment prer.aure spray systein.
In the event of a loss of Coolant Accident.
Spect rication :
SP"CIIIC"lI "I
A.
Once each operett:.g cycle, the following A.
During power operation, both of the two containment spray systems shall 1
Automatic actuation of the contain-be operable.
ment spray valve Mo-To68: (with water flow manually blocked).
B.
If Specification A is not met, a nonnal orderly shutdown shall be initiated with-2 Calibration of flow instrumentation.
In 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the reactor shall be shut down as described in Section 1.2.$(a) within 11 At least once every refueling outage, not 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and shutdown as described in to exceed eighteen (10) months, the follow-Section 1.2.5(a) and (b) w!Lhin the ing shall be perronned prior to startup:
following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..
Veri fy operability of power-operated valves C.
Opera >bility of the fire water supply required for pmper syr. tem actuation.
and recirculation systems is governed hy Speci fication 11.3.1.4.
C.
Surveillance or fire water supply and recirculation systems is governed by Spect rication 11.b.1.4.
D.
Instrument channels shall be tested and calibrated as listed in Table 11.4.3.la(a).
E.
Deleted 1
11-14 Amendment No. 37 I
TAllt.E 11.h. 3.b instetsmentation That init.tates Diclosure Sprny.
- 11. 3.1.h I.ini ting Condi tions for Operation 11.b.3.b Surveillance Hergist rement Instrument Trip Trip System Conditions for Test Including In s t rtment Parnmeter logic Get Point Operability Valwe Actuation Calibration Fnclosure Hid 1 of 2
$ 2.2 psig (a)
Power Operation Each re fueling outage Each re fueling Pressure Taken twice not to exceed eighteen outage not to Time Delay Deleted (18) sw>nths (a) Primary enclosure spray setting (b) Del eted 11-15 Amendment No. 37
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