ML19323A120

Revised Pages to Tech Specs Re Station Fire Hose Hydrostatic Test Pressure & Flexibility in Min Shift Crew Composition

ML19323A120
Person / Time
Site:	Peach Bottom
Issue date:	04/15/1980
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19323A112	List: ML19323A111 ML19323A116 ML19323A120
References
NUDOCS 8004170256
Download: ML19323A120 (10)

Text

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TABLE 3.2.B INSTPUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No.  ; o ,

of Operable Number of Instru-Instrument Trip Function Trip Level Setting ment Channels Pro Remarks

. Channels Per vided by Design Trio System (1:

? Reactor Low-Low 2-48 in. indica ted 4 HPCI S RCIC Initiates HPCI S PCIC l Water Level icvel Inst. Channels 2 Reactor Low-L3w-Low- 2-160 in. indicated 4 Core Spray 6 1. In conjunction with Water Level level (4) RHR Instrument Low Reactor Pressure Channels initiates Core Spray

.and LPCI e

4 ADS Instrument -

Channels E 2. In conjunction with confirmatory low

' level High Drywell Pressure, 120 second time delay and LPCI 0D or Core Spray pump C interlock initiates o Auto Blowdown (ADS) c.

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3. Initiates starting

$$ of Diesel Generators g) 50 6'

PBAPS hl_HITING CONDTTIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A.6.c (Cont'd) 4.7.A.6.c. (Cont ' d) the affected reactor must ** The CAD system H2 and O2 he taken out of power analyzers shall be tested operation. for operability using '

standard bottled H2 and 02 .

once per month and shall be calibrated once per 6 months. The atmosphere analyzing system shall be functionally tested once per operating cycle in conjunction with specification 4.7. A.6.a.

Should one of the two ,

H2 or 02 analyzers serving the drywell or suppression pool be found inopereble the remaining analyzer of the same type serving the same compartment >

shall be tested for operability once per week until the defective analyzer is made operable.

d. A 30 psig limit is the maximum containment repressurization allowable using the CAD system. Venting via the SBGT system to this stack must be initiated at 30 psig following the initial peak pressure of 49.1 psig.

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PDAPS LIMITi tiG CollDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A.7 If the specifications of 3.7.A.1 through 3.7.A.5 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 ,

hours.

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PBAPS I.1 MI 'll!3G CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 1.9.B {Rw'r.3 tion with Inoperable 4.9.B ljunipment whenever the reactor is in Run Mode or Startup Mode with the reactor not in a Cold Condition, the availability of electric power shall be as specified in 3.9.A, except as follows:

1. From and after the date incoming power is not available from one startup or emergency transformer, continued reactor operation is permissible for seven -

days. During this period, the four diesel generators and associated emergency buses must be demonstrated to be operable.

2. From and after the date that incoming power is not available from both start-up -

or emergency transformers, continued operation is permissible, provided the four diesel generators and associated emergency buses are operable, all core and containment cooling systems are operable and reactor power level is reduced to 25%

of the design.

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PDAPS blNITIIM cot 3DITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3 . 9 . 16 (Cont'd) 4.9.B

3. From and after the date that one of the diesel generators or ascociated emergency bus is made or found to be inoperable for any reasons, continued reactor operation is permissible in accordance with Specification 3.5. F if Specification 3.9. A.1 is satisfied.

4. From and after the date that one of the diesel generators or associated emergency buses and either the emergency or startup transformer power source are made or found to be inoperable for any reason, continued reactor operation is permissible in accordance with Specification 3.5.F, provided the other off-site source, startup transformer and emergency transformer are available and capable of automatically supplying power to the 4KV emergency buses.

S. From and after the date that one of the 125 volt battery systems is made or found to be inoperable for any reason, continued reactor operation is permissible during the succeeding three days within electrical safety considerations, provided repair work is initiated in the most expeditious manner to return the failed component to an operable state, and Specification 3.5.F is satisfied.

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PBAPS J.IMITIiM CONDITIONS FOR OPERATION SURVEILLANCE FEQUIREMENTS J.10 Col (E Al.TERATIONS 4.10 CORE ALTERATIONS Applicability Applicability Applies to the fuel handling Applies to the periodic ,

and core reactivity limit- testing of those interlocks ations. and instrumentation used during refueling and core alterations. .

Obiective obiective To ensure that core reactivity To verify the operability is within the capability of of instrumentation and the control rods and to pre- interlocks used in refueling vent criticality during and core alterations.

refueling.

Specification Specification A. Pefueling Interlocks A. Refueling Interlocks i

1. The reactor mode switch 1. Prior to any core altera-shall be locked in the tations within or over the

" Refuel" position during reactor core, the reactor core alterations and the switch " Refuel" position refueling interlocks interlocks shall be shall be operable except functionally tested.

as specified in 3.10.A.5 and They shall be tested 3.10.A.6 below. at weekly intervals thereafter until no longer required. They shall also be tested following any repair work associated with the interlocks.

2. Fuel shall not be loaded 2. Prior to performing control into the reactor core un- rod or control rod drive less all control rods are maintenance on control i fully inserted. cells without removing i fuel assemblies, it shall be demonstrated i that the core can be made subcritical by a margin of 0.25 percenta k at any time during the maintenance with the strongest operable control rod l

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PBAPS I IMITIIIG CONDITIOt18 FOR OPERATION SURVEILLANCE REQUIREMENTS - 3.10.A Itefueling Interlocks 4.10.A.2 (Cont'd) fully withdrawn and all other operable rods

3. The fuel grapple hoist load fully inserted. Alternatively nwitch shall be set at $1000 if the remaining control roda lbs. are fully. inserted and have their directional control

4. If the frame-mounted valves electrically dis-auxiliary hoist, the monorail- armed, it is sufficient mounted auxiliary hoist, to demonstrate that or the service platform the core is subcritical hoist is to be used with a margin of at for handling fuel with least 0.255 A k at any the head off the reactor time during the main-vessel, the load limit tenance. A control switch on the hoist to rod on which maintenance be used shall be set at is being performed

< 400 lbs. shall be considered inoperable.

5. A maximum of two nonadjacent control rods may be withdrawn from the core for the purpose of performing control rod and/or control rod drive maintenance, provided the following conditions are satisfied:

a. The reactor mode switch shall be locked in the

" refuel" position. The refueling interlock which

• prevents more than one control rod from being withdrawn may be bypassed for one of the control rods on which maintenance is being performed. All other refueling interlocks shall be operable.

b. A sufficient number of contrcl rods shall be operable so that the core can be made subcritical with the strongest operable control rod fully withdrawn anil all other operable controls rods fully inserted, or all

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PBAPS i LIMITING COllDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.14.A (Cont ' d) '

c. Turbine Building c. Hose station valve

d. Circulating Water Pump Structure operability and blockage check - once every 3 years.

6. Wher. a hose station serving d. Hose hydrostatic test at an area which contains a pressure at least equipment which is required 50 psig greater than to be operable becomes the maximum pressure inoperable, establish a available at that hose continuous fire watch station but not less equipped with portable than 150 psig fire suppression equip- with an appro,or replace priately ment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> tested hose-every 3 years and provide equivalent protection to the area 6. None served by the inoperable station from the operable hose station within 6 -

hours.

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7. Except as specified in 7. The SGTS fire suppression 3.14.A.8 below, the spray system testing fire suppression shall be performed as spray system serving a follows: I Standby Gas Treatment I system charcoal filter a. Simulated automatic train shall be operable actuation test - once when a train is required every 18 months. <

to be operable.

8. If the requirements of 3.14.A.7 b. Inspection of nozzles cannot be met, and spray header- .

once every 18 months '

a. establish a fire water patrol to inspect the c. Header and nozzle air area with inoperable flow test - once every fire suppression 3 years equipment at least once per shift.

b. restore the system to an operable status within 14 days, or in lieu of any other report required by Specification 6.9.2 submit a Special Report to the Commission pursuant l to Specification 6.9.3 within l

31 days outlining the.cause of l the malfunction and the plans for restoring the system to an i operable status. The SGTS may  !

he considered operable for the I purposes ut Specification 3.7.B.

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-PDAPS j i

6.0 ADMINISTRATIVE CONTROLS i

6.1 Recronsibility 6.1.1 The Station Superintendent shall be responsible for overall facility operation. In the absence of the Station i Superintendent, the Assistant Superintendent or the Engineer-  ;

Technical (or any other person that the Station i superintendent may designate in writing) shall, in that- I order, assume the Superintendent's responsibility for overall .

facility operation.

6.2 Organization Offsite 6.2.1 The offsite organization for facility management and technical support shall be as shown On Figure 6.2-1.

Facility Staff 6.2.2 The facility organization shall be as shown on Figure 6.2-2 l and: -

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Figure 6.2-2,  !

except that the shift crew composition may be less than  !

the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate.  ;

action is taken to restore the shift crew composition to within the minimum requirements.

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b. At least one licensed operator shall be in the control room and assigned to each reactor that contains fuel.

c. At least two licensed operators, excluding the operator .

on the second unit, shall be present in the control room t

, during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips. ,

d. An individual qualified in radiation protection procedures shall'be on site when.fael is in the reactor.

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, e. All CORE ALTERATIONS shall be directly supervised by.

either a licensed Senior-Reactor Operator or' Senior Reactor Operator Limited to Fuel Handling who has no  ;

other concurrent responsibility during.this operation. ,

l f. A Fire-Brigade of'at least 5 members shall be maintained-onsite at all' times. The Fire Brigade shall not include

7the minimum shift crew necessary.for safe shutdown of-

• i the unit (s). (3 members) or any personnel required for j other essential functions during a fire emergency. -

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PBAPS 6.5.2 operat i.on and safety Review Commitee Function 6.5.2.1 The Operation and Safety Review Committeee shall function to provide independent review and audit of designated activities in the area of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. Radiological safety

g. mechanical and electrical engineering

h. quality assurance practices The members of the OSR Committee will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CFR 50, Appendix B. Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance Organization available to them.

Organization 6.5.2.2 The Chairman, Members and alternate Members of the OSR Committee shall be appointed in writing by the Vice l President, Electric Production, and shall have an academic degree in an engineering or physical science field; and in

' addition, shall have a minimum of five years technical experience, of which a minimum of.three years shall be in one or more areas given in 6.5.2.1.

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