Text

Amend 78 to License DPR-6,modifying Tech Specs by Implementing Definition of Operability & Incorporating Limiting Conditions for Operation for Redundant Safety Sys
	ML20137W310
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	10/02/1985
From:	Zwolinski J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20137W307	List: ML20137W303; ML20137W310; ML20137W323;
References
	NUDOCS 8510040277
	Download: ML20137W310 (12)
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%, UNITED STATES 3[' n NUCLEAR REGULATORY COMMISSION 5 j WASHINGTON, D. C. 20555 l

CONSUMERS POWER COMPANY g.-

l DOCKET NO. 50-155 ; p. _

BIG ROCK POINT PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. DPR-6

1. The Nuclear Regulatory Comission (the Commission) has found that:

. A. The application for amendment by Consumers Power Company (the licensee) dated November 14, 1984, as revised on January 17, 1985, 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 (1) that the activities authorized by this amendment ~can be conducted without endangering the health and safety of the public; and s (ii) that such activities will be conducted in compli-ance 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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l 8510040277 85 ADOCK

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2. Accordingly, the license is amended by changes to the TecIhr,iical Specifications as indicated in the attachment to this license -

amendmentandParacraph2.C.(2)ofFacilityOperatingLicefse No. DPR-6 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 78, 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 OPMISSION '

. A T w (.

John A. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 2, 1985.

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ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. DPR-6 . ,.

DOCKET N0. 50-155 -

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.i Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised peces are identified by the captioned amendrnent number and contain marginal lines indicating the area of change.

REMOVE INSERT 1-2a 1-2a 3-3 3-3 3-4 3-4 3-4a -

3-5 3-5 4-6 4-6 11-2 11-2 11-7 11-7*.

11-8 11-8 11-14 11-14 s

Page issued to maintain document completeness.

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1.2.8 OPERABLE - OPERABILITY - a system, subsystem,. train, component or device shall be OPERABLE or have OPERABILITY when it is capable of per-forming its specified safety function (s). Implicit in.t'his definition shall be-the assumption that all necessary attendant ins,trumentation, controls, electrical power sources, cooling or seal watqt, lubrication or other auxiliary equipment that is required for the system, subsystem, train, component or device to perform its safety function (s) are.also capable of performing their related support function (s).

1.2.9 CHANNEL CALIBRATION - adjustments, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The channel calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Functional Test. The channel calibration may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

1.2.10 CHANNEL CHECK - the qualitative assessment of channel behavior during operation by observation. The determination shall include,

_ where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

1.2.11 CHANNEL FUNCTIONAL TEST

a. nalog Channels - the injection of a signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.

b. Bistable Channels - the injection of a signal into the sensor

- to verify operability including alarm and/or trip functions.

1.2.12 SOURCE CHECK - the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

1.2.13 MEMBERS OF THE PUBLIC - includes all persons who are not occupationally associated with the plant.

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1-2a AmendmentNo.f4I,JY',78

3.4.2 (Contd) closesautomaticallywhenevernecessarytoprerentout,w{rdflowin 1 the event of an accident. Except for check valves, both valves shall be capable of being closed by manual initiation ftom S either the control room or from other stations that would bertJnable ~

! after an accident.

(c) Lines open to the reactor vessel or any portion of the reactor recirculation loop are treated in the manner described in the previous. paragraph, with the added feature that the two valves shall be on opposite sides of the shell of the containment sphere.

(d) Lines normally closed have only a single valve. A lock, inter-lock, or operating rules shall insure that this valve is closed whenever containment integrity is required.

(e) Certain lines enter and leave the containment sphere without any openings to the containment sphere free volume. Others leave and return to the containment sphere without any openings to the atmosphere. Such lines shall not require isolation valves, .

provided the lines are not in danger of being broken as a result of a reactor system rupture.

(f) The two 24-inch ventilation openings, one for supply and one for exhaust, shall be designed to close within six seconds after any scram signal or on high radiatica at either of two area monitors in the fuel storage area. In order to prevent the possibility of excessive _axternal pressure on the containment sphere due to

_3, atmospheric changes or other causes, the two valves in the ventilation supply line and the two valves in the ventilation exhaust line shall automatically open whenever the differential pressure exceeds 1 psid, overriding all other signals. The valves shall reclose when the internal pressure is still slightly below atmospheric.

3.4.3 Operating Requirements (a) Normally open lines, e,rryL.; fluids out of the containment t 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 costainment sphere, shall be equipped with check valves to prevent m.,

backflow upon loss of inward propellent force. In addition, these lines shall be capsble 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 3-3 Amendment No.,A9", 78 l

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l 3.4.3 (Contd) of the supply line to the control rod drive hydraulic system.

Valves in this control rod hydraulic system line shall open to insure continuous water supply, and backup isolation shell .be provided by two check valves in the conmon suction line to the control rod drive pumps. I p. -

(c) Closing times on motor-operated isolation valves shall bIe as follows:

Description Closing Time (Seconds)

Main Steam (M0-7050) 60 Main Steam Drain (MO-7065) 60 (d) ~If both vacuum relief paths described in Section 3.4.2(f) become inoperable during power operation, the plant shall be brought to

^

shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to the cold shutdown-condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If one vacuum relief path becomes inoperable and cannot be restored to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the plant shall be brought to shutdown condition within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and to the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.5 PC'ST-INCIDENT SPRAY SYSTEM Containment effectiveness shall be supplemented by a containment sphere post-incident spray system in the event of an accident involving loss of coolant from a primary system rupture.

._, 3.5.1 Design Features Shall Be as Follows:

(a) Number of Sets of' Spray Nozzles 2 (b) Capacity of Spray Sets at 100 Psid Nozzle Pressure (1) Primary Spray Set, Gal / Min 146 (ii) Secondary Spray Set, Gal / Min 233 (c) System Actuation (1) Primary Spray Set Automatic DC Operated (ii) Secondary Spray Set Remote Manual AC Operated (d) Signal Used to Actuate High Containment Sphere Pressure (e) Signal Trip Setting 5 2.2 Psig (f) Reserve Water Supply Lake Michigan Amendment No. [ df , 78 3-4 l

3.5.2 Operating Requirements (a) Deleted a .

- 1 (b) Water addition to the containment sphere must'b6 manually stopped before the accumulated water level reaches an ele-vation of 596 feet. f. .

(c) Deleted j 3.6 CONTAINMENT REQUIREMENTS i

Containment sphere. integrity shall be maintained during power opera- l tion, refueling operation, shutdown and cold shutdown conditions except as specified by a system of procedures and controls to be established :

for occasions containment must be breached during cold shutdown. If ,

containment integrity cannot be maintained, the plant shall be brought to the shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and to the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . i

'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

_s, 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 leakage testing.shall be:

(a) At least once every 6 months, the personnel lock, the aquip-

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ment lock and the sphere supply-and-exhaust ventilation valves shall be pressurized, with air to 20 psig, to test their leak tight-Y 3-5 AmendmentNo.)d,k,78 l

4.1.2 -(Centd)

Minimum Time to Put System 30 in Full Operation Following Signal, Seconds Core Spray System:

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Type Sparger Ring With 'Sp' ray Nozzle Capacity of Sprays, Gpm 400 i. -

Nozzle Pressure, Psia. 115 :

J Backup Core Spray System:

Type Sparger Nozzle Centered Over Core Capacity of Sparger, Gpm 470 ;

Nozzle Pressure, Psia 115 Core Spray System Recirculation:

Number Pumps 2

_ Number Heat Exchanger .1

-Heat Removal Capacity, Btu /h 8 x 10 6 6 28.4*F Log Mean Temperature Difference (b) Operating Requirements A minimum of one reactor recirculating loop shall be used during all reactor power operations (ie, recirculating pump suction valve and 20" discharge valve shall remain open and pump shall be running).

The maximum operating pressure and temperature shall be the same as the reactor vessel. The controlled rate of change of temperature in the reactor. vessel shall be limited to 100*F per hour. All other

s. components in the system shall be capable of following this tempera-ture change race. The safety relief valves shall be set appropri-ately for all planned reactor operating pressures so that the allowable pressure of 1870 psia (1700 plus 10%) in the nuclear steam l supply system is not exceeded. At least three (3) steam drum safety j valve position monitors shall be operable during power operation. J Also, one of every two (2) adjacent monitors oriented in each north- '

south plane shall be operable. In the event that any of these monitoring channels become inoperable, they shall be made cperable prior to startup following the next cold shutdown. The emergency condenser shall be operable and ready for service at all times during power operation. However, should one emergency condenser tube bundle develop a leak during power operation.-it will be permissible to isolate the leaking tube bundle until the next outage. Both bundles of the emergency condenser shall be available for service during cold to hot plant heatup for power production.

If both emergency condenser loops become inoperable the plant shall be brought to shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to to1d shutdown condition within the folloving 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The shutdown cooling system shall be ready for service during power operations with the 480. volt circuit breakers for isolstion valves MG-7056, MO-7057, MO-7058, and MO-7059 checked "open" when reactor pressure is above 300 psig. The shutdown cooling system shall be operablie and ready for service during refueling operations and the breakers for MO-7070 and MO-7071 shall be tagged "open". The primary coolant shall be saapled and analyzed dail during periods of power operation. The following are absolute limits whiefifexceededshallnecessitatereactorshutdown.Correctiveaction will necessarily be taken at more stringent limits to minimize the Possibility of these absolute limits ever being reached.

I 4-6 AmendmentNo.)d,h,/,78 l

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1.1uiting Candition icr Optretion Surveillance Requirement *

!!.3.1.4 EMERGENCY CORE C001.ING SYSTEM (Contd) 11.4.1.4 EHERCENCY CORE CODI.ING SYSTEM (Contd)

D. Both fire pumps (electric and diesel) and B. At each major refueling outage, the the piping system to the core spray systems following shall be performed:

tie-ins shall be operable whenever the plant is in a power operation condition and refueling. Calibration of core spray system actuation and pressure and flow instrumentation.

E. If Specifications A, B, C, and D are not met, j a normal orderly shutdown shall be initiated Verify that the two core spray system I

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the reactor shall be containment isolation check valves are not shut down as described in Section 1.2.5(a) stuck shut, within twelve (12) hours and. shut down as described in Section 1.2.5(a) and (b) within Calibration of fire system basket strainer the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . No work shall be differential pressure switches, performed on the reactor or its connected systems when irradiated fuel is in the reactor Operability check of the core spray

, vessel which could result in lowering the recirculation system through the test i reactor water level below elevation 610' 5". tank flow path. During the core spray i

recirculation system operability check F. If both core spray systems become inoperable, reduce any leakage to as low as practical i the plant shall be brought to shutdown from components outside containment prior i

H condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to the cold to returning system to service.

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shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Verify manual and automatic actuation of the core spray system valves NO-7051. -7061. -7070,

, C. Instrument set points shall be as specified and -7071 with water flow normally blocked.

in Table 11.3.1.

3 Verify manual actuation of H0-7066.

t l Verify that the hose used for backup cooling water to the core spray recirculation heat

, exchanger la operable and free of obvious defects.

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Perform a leak check and flow check of the backup f[

o cooling water hose when connected between the

o. screen house fire water connection and the core sprayrecirculationheatexchegger) ,

I o W-re 1 i C. Instruments shall he checked, tested,iand se calibrated at least as frequently 8as Ifsted l ? in Table 11.4.1.4(a).

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(NOTli: %is is the new format of the Specifications to be issued in the future. %crefore, the numbering. system may conflict kith existing sections. Both are still applicable.)

Limiting Conditions for Operation Surveillance Requirement 3.1 - S REACTOR DEPRESSUR12ATION SYSTEM

. 4.1.S REACTOR DEPRESSURIZATION SYSTt!M Applicability': Applicability:

j Applies to the operating status of.the Reactor Applies to periodic testing requirements for Depressurization System (RDS) and the attached the RDS and tne attached mechanical snubbers.

mechanical snubbers. -

objective: Objective:

l To assure the operability of the RDS and when To veri fy operability of the RDS.

i working in conjunction with the emergency core cooling system to allow cooling of the reactor Speci fication: ,

fuel in the event of a Loss of Coolant Accident.

A. %c isolation valves shall be test-operated

, y Specification: at 1 cast once every three months.

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A. We RDS shall be operable at all power i levels and when the reactor is critical with the head on or when in hot shutdown B. % d depressurizing valves shall be test-i conditions. operated during each cold shutdown; how-s i . cver, in the case of frequent cold shut-

. B. We limiting conditions for operation of downs, these valves need not be exercised the instrument'a tion and actuating circuitry more often than once every three months per which initiates and controls the RDS arc. .

Section IWV-3410 Simoner 1973 Addenda of the given in Table 3.5.2.h. ASME DGPV Code Section XI.

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Action: C. %c instrumentation shall be functionally

, 1. Shou)d one depresdurizing valve or . tested,. calibrated and ch'elked

' ' ' ' ' ' ' ag indi-

" isoihtion valve become inoperable in the d h hm C5h ,.

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@ closed position, the reactor may remain in i -

operation for a period not to exceed seven j h (7) days. The remaining valves and

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I l Limiting Conditions for Operation Surveillance Requirement i 3.1.5 REACTOR DEPRESSURIZATION SYSTEM (Contd) 4.1.5 REACTOR DEPRESSURIZATION SYSTEM (contd)

! actuating circuitry shall be demonstrated D. System 1.ogic shall also be functionally l to be operable within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and at least tested as indicated in Table 4.5.2.h.

i ence each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months until the system is j restored to operable status. E. Should one input or output channel fail, j the remaining three channels shall be

2. Should one isoletion valve or depressurizing tested within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and at least once I

i valve become inoperable in the open position each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months until the system is restored I

during power operation, the plant will be to normal.

brought to the cold shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . F. The UPS battery surveillance is i described in Section 11.4.5.3.

3. Only one RDS valve train, one input channel, one output channel aridone UPS power supply C. The BDS containment penetration assemblies may be out of service at any one time. If seal pressure shall be examined at j these components are not returned to six-month intervals.

j operable status within seven (7) days, a normal orderly shutdown shall be initiated H. A visual inspection of 101 (2) of the b [ within one-(!) hour and the reactor shall . thirteen mechanical snubbers on the RDS l

$ be shutdown as described in Section 1.2.5(a) shall be performed at each refueling outege l within twelve (12) hours and shutdown as but not to exceed 18 months. Visual i

described in Section 1.2.5(a) and (b) within inspections shall be used to verify that the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . there are no visible indications of i damage or impaired operability to the '

4. If the RDS is declared inoperable because of a anubbers or their attachments.

j snubber defect and is not returned to an l operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the plant shall I. A functional test of 101 (2) of the j be brought in a normal and orderly manner to a thirteen mechanical snubbers on the RDS

! cold shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and be shall be performed at each refueling outage 1 maintained in cold shutdown until RDS can be but not to exceed 18 months. Functional l g declared operable. If the plant is already in a cold shutdown condition it shall not be testo shall be used to verify that the i m force that initiates free movement of the j [ started up until all snubbers are operable, snubber rod. In tennion and compression, l 9 Is less than the vendor specifigd'

5 '. Shoind two or more RDS valve trains become maximum drag force. Activation U sErainIng l inoperable the plant shall be brought to the action shall be achieved within the vendor

@ shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to specified range of velocity or acceleration the cold shutdown condition within the in both tension and compression.

following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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Limiting Conditions for Operation Surveillance Requirement 11.3.3.4 CONTAINMENT SPRAY SYSTEM 11.4.3.4 CONTAINHENT SPRAY SYSTEM Applicability: Applicabilitys j Applies to the operating status of the Applies to the testing of the containment

] containment spray system. spray system.

Objective: Objective:

To assure the capability of the To verify the operability of the containment containment spray system to reduce spray system.

containment pressure in the event of a Loss of Coolant Accident. Specification:

Specification: A. Once each operating cycle, the

, following shall be performed:

A. During power operation, both of the l two containment spray systems shall 1. Automatic actuation of the

,, be operable. containment spray valve HO-7064 Fa (with water flow manually blocked).

d. B. If Specification A is not met, a normal j

orderly shutdown shall be initiated 2. Calibration of flow instrumentation.

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the reactor shall be shut down as described in Section B. At least once every refueling outage, 1.2.5(a) within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and shut down not to exceed eighteen (18) months, I

as described in Section 1.2.5(a) and (b) the following shall be performed prior within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . to start-up.

C. Operability of the fire water supply Verify operability of power-operated and recirculation systems is governed valves required for proper system by Specification 11.3.1.4. actuation.

$I m D. If both containment spray systems become C. Surveillance of fire water supply and S. Inoperable the plant shall be brought recirculation systems in governed.by, ,

$ to shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Specification 11.4.1.4. . . , , , , ,.

S fbhdtothecoldshutdowncondition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . D. Instrument channels shall be tested and ',,

!f

. calibrated as listed in Table ll.4.1.4(a).

g E. (Deleted)

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ML20137W310

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