ML20097C903

Proposed Tech Specs Re Operability & Surveillance Requirements for Standby Shutdown Sys

ML20097C903
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/07/1984
From:	DUKE POWER CO.
To:
Shared Package
ML20097C900	List: ML20097C897 ML20097C903
References
NUDOCS 8409170300
Download: ML20097C903 (10)

Text

p PLANT SYSTEMS.

3/4.7.14 STANDBY SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION

~3.7.14 The Standby Shutdown System (SSS) shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With the Standby Shutdown System inoperable for more than 7 days, prepare and submit a Special Report to the Commis-sion pursuant to Specificatitsn 6.9.2 within the next 30 days outlining the cause of the inoperability, corrective actions being taken, and plans for restoring the system to OPERABLE status; and

b..With one or more SSS components inoperable, as determined by the performance of surveillance requirements of Specification 4.7.14, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify the OPERABILITY of fire detection and suppression systems (if installed) in areas as identified in Table 4.7-2 and, as appropriate, perform the actions identified in notes 3 and 4 of the table.

With the tot:al leakage from UNIDENTIFIED LEAKAGE, IDENTI-c.

FIED LEAKAGE and reactor coolant pump seal leakoff greater than 26 gpm, declare the Standby Makeup Pump inoperable and take ACTIONS a. and b., above.

d.

If equipment which constitutes inoperable component of SSS is located inside containment, then repairs shall be effected at the first outage which permits containment access.

If the diesel generator is inoperable, repairs shall be e.

effected within 60 days, or a rerort shall be prepared within the next 14 days which:

1) details the extent of

- repairs required, 2) outlines the schedule for completion of those repairs, and 3) provides a basis for continued operation.

f.

The provisions of Specifications 3.0.3 and 3.0.4 do not apply.

SURVEILLANCE REQUIREMENTS 4.7.14.1 The Standby Shutdown System di sel generator shall be demon-strated OPERABLE:

At.least once per 31 days by verifying:

a.

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1).The fuel level in the fuel storage tank is greater than.or equal to 4.0 feet, and 3

2) The diesel starts from ambient conditions and operates for at least 30 minutes-at greater than or equal to 700 kW.

b. -By sampling new fuel oil in accordance with ASTM D4057-81 prior to addition to the storage tanks and:

1) By verifying in accordance with the tests specified in ASTM D975-81 prior to addition to the storage tanks that the sample has:

a) An API Gravity of within 0.3 degrees at 60 F or-

-a specific gra/ity of within 0.0016 at 60/60 F, when compared to the supplier's certificate or an

-absolute specific gravity at 60/60 F of greater than or equal to 0.83 but less than or equal to 0.89 or an API gravity at 60 F of greater than or equal to 27 degrees but less than or equal to 39 degrees.

b)-

A kinematic viscosity at 40*C of greater than or equal to 1.9 centistokes but less than or equal

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to 4.1 centistokes (on a Saybolt Universal Viscosity at 100 F of greater than or equal to 32.6 SUS but less than or equal to 40.1 SUS).

c) ' A flash point equal to or greater than 125 F, and d) A clear and bright appearance with proper color when tested in accordance with ASTM D4176-82.

2) By verifying within 31 days of obtaining the sample

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that the other properties specified in Table 1 of ASTM 0975-81 are met when tested in accordance with ASTM D975-81 except that the analysis for sulfur may be performed in accordance with ASTM D1552-79 or ASTM D2622-82.

c.

At least once per 18 months by subjecting the diesel to an inspection in accordance with procedt'res prepared in conjunction with its manufacturer's recommendations for the class of service.

4.7.14.2 The Standby Shutdown System diesel starting 24-volt Nickel-Cadmium battery bank and charger shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that the overall L

battery voltage is greater than or equal to 24 volts, b.

At least once per 18 months by verifying that:

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1) The batteries and battery racks show no visual indi-cation of physical damage or abnormal dete.r,ioration, and

2) The battery-to-battery and terminal connections are clean, tight, and free of corrosion.

4.7.14.3 The Standby Makeup Pump water supply shall be demonstrated OPERABLE by:

Verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that IDENTIFIED a.

LEAKAGE, UNIDENTIFIED LEAKAGE, and Reactor Coolant Pump Seal leakoff do not exceed a total of 26 gpm.

b.

Verifying at least once per 7 days:

1) That the requirements of Specification 3.9.10 are met and the boron concentration in the storage pool is greater than or equal to 2000 ppm, or

2) That the refueling water storage tank is capable of being aligned to the Standby Makeup Pump.

Verifying at least once per 92. days that the Standby Make-c.

up Pump develops a flow of greater than or equal to 26 gpm at a pressure greater than or equal to 2485 psig.

4.7.14.4 The Standby Shutdown System 250/125-Volt Battery Bank and its associated charger shall be demonstrated OPERABLE:

At least once par 31 days by verifying:

a.

1) That the electrolyte level of each battery is above the plates, and

2) The total battery terminal voltage is greater than or equal to 258/129 volts on float charge.

b.

At least once per 92 days by verifying that the average specific gravity is greater than or equal to 1.200.

At least once per 18 months by verifying that:

c.

1) The batteries, cell plates, and battery racks show no visual indications of physical damage or abnormal deterioration, and

2) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

4.7.14.5 The Steam Turbine Driven Auxiliary Feedwater Pump and associ-ated components shall be demonstrated OPERABLE at least once McGuire - Units 1 and 2 3/4 7-49 a

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per '18 months by verifying that the "C" solenoid is capable of being-deenergized to open valve SA48ABC to provide steam supply to the turbine driven auxiliary feedwater pump.

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.4.7.14.6 Standby Shutdown System instrumentation shall be demonstrated OPERABLE by performance of surveillance requirements listed in Table 4.7-3.

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7., :,0 TABLE 4.7-3 P.'

MINIMUM CHANNEL CHANNEL READOUT CHANNELS Instrument CHECK CALIBRATION LOCATION OPERABLE Reactor Coolant Pressure M

R SSF Control-1 Panel Pressuri,zerL Level M

R SSF Control-1

' Panel SieamGenerator_ Level M

R SSF Control 1/S.G.

. Panel Incore' Temperature M

R SSF Control 1

' Panel Standby Makeup Pump Flow N/A R

SSF Control 1

Panel k

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TAntE'4.7-7 g.

.t.m.m.y '.liut.t..wie :.ystem Cagnwnt AC110N Statenistreith.

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-a E'

With 'one or more of the following Verify operability (*

of:ffre detectors and SSS components inoperable

[

suppression syste.es (if installed) in the '

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following areas

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~N 1

EL 716 EL 73'3 'EL 750.. Control. Battery Cable Turbine Driven. Motor Drivene Containment Other EE-KK EE-KK ;EE-KK

. Room

.Roca '. Rooms AFW Pump -

AFW Pump 3

' Actions A.

Diesel Generator X

X

'X'

.X

.X X

.X.

X

-(2)'

(3),(4)'

B.

Diesel starting 24-Volt battery X

X-X X-

-X X_

X'

.X (2)

.(3),(4)

. bank and charger.

C.

Standby makeup pump and water supply X

.X X

7 D.

250/125 V battery bank and associated E

charger X

X X

(2).

(4)-

E.

Steam Turbine Driven Auxiliary Feedwater -

Pump Solenoid "C" X

F.

Instrumentation l

Reactor Coolant Pressure X

X X

l Pressurizer Level (2)'

X-X X

Steam Generator Level (2),

X X

X Incore Temperature (2)

X X

X (2)

NOTES: (1)

If fire detection and/or suppression systems are inoperable, then the ACTION statement (s) of the appilcable fire detection and/or :

suppression technical specification (s) shall be co.aplied with.

(2)

Monitor containment air temperature at least once per hour at the locations specified in Specification 4.6.1.5.1 or 4.6.1.5.2 lieu of verification of operability of systems inside containment.

. in (3)

With this component inoperable, verify operability of off-site power and one blackout diesel generator.

(4)

With this component inoperable, then denoted areas of both units are affected.

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ATTACHMENT II A.

Technical Justification The Standby Shutdown System (SSS) provides an additional degree of redun to the multiple systems which are available, under emergency conditio achieve and maintain the reactor in the Hot Standby Mode.

ns, to requirements and action statements presented in the Draft Technical Specification The surveillance of this redundant system.are reasonable considering the safety significance of a po By design, the SSS is intended to respond to those low probability fire and/or sabotage events which render both the control room and automatic safety systems inoperable.

Because of the low probability of occurrence of these events, the action statements in the proposed specifica-if necessary, a justification for continued operation. tion rely on c Because the SSS performs a redundant fire protection function, compensatory action relies largely.on assurance of the operability of fire detection and suppression systems.

Tabic 4.7.2 of the proposed specification establishes requirements for operability of fire detection and suppression systems.

=

The surveillance requirements presented in Attachment I are intended to provide assurance that the various components of the Standby Shutdown System (SSS) per-form their functions.

=

ing SSS Technical Specification for the Catawba Nuclear StationThe surveill

, which was ap-proved prior to the issuance of the fuel load license for Unit 1 of that plant.

Also considered in the formulation of the surveillance requirements were exist-ing McGuire Technical Specifications, such as those for the 1E Diesel G Refueling Water Storage Tank, Fire Protection & Detection Systems, and other enerators, Tech Specs which are related to the safe operation and/or shutdown of the plant Following is an item-by-item justification of the proposed Technical Specification 3.7.14 - Action Statements The SSS Technical Specification for Catawba requires that with the SSS inoperab a

restore the inoperable equipment to operable status within 7 days or be in at e,

least hot standby in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Considering that the SSS is a third line of defense for a low-probability fire i

event, it is not reasonabl when a component of the system is inoperable.e to require a plant shutdown for those occas 4.7.14.1.C requires that every 18 months, For example, specification i

to an inspection which involves a suLstantial disassembly.the diesel generator be sub to expect that thin inspection can be performed within 7 days.It ic not reasonable a multi-unit plant such as McGuire, both units would have to be shut doun eve Therefore, at 18 months for an extended outage, presumably in addition to at refueling outage.

least one unit's

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ACTION STATEMENT C, Regarding total allowed leakage, is virtually <the same as Catawba's. The quantities of identified and unidentified leakage allowed

are governed by specification 3.4.6.2, " Operational Leakage." The allowance r

for Reactor Coolant Pump Seal Leakoff.~ (15 GPM)- is a conservative amount which is almost (3.75 GPM/ Pump vs. 4.3) equal to the degraded seal performance

.value used as the design basis. The.55 CPM / Pump difference is not a safety Concern.

ACTION STATEMENT D, Recognizes that equipment inside containment is inaccessible during operation. As noted'previously, it is not reasonable to require a shut-

.down to repair an inoperable component of the SSS. However, any inoperable

-equipment.will be repaired at the first available opportunity (i.e., Planned or forced outage.)

. ACTION STATEMENT E. Provides an adequate length of time to repair or inspect the diesel generator. During this time, at least one emergency diesel and off-site power will be operable.

The verification of operability of fire detection and suppression systems in the locations specified in Table 4.7.2 will provide adequate assurance that those.

- Esystems for which the SSS provides a backup will not be damaged by fire.

4.7.14 - Surveillance Requirements

'4.7.14.1

.a.

1) A fuel level of 4.0 feet in the fuel storage tank is sufficient to operate the diesel for at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

It is assumed that, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, off-site power can be restored or additional fuel can be added to the storage tank.

2) This specification is. identical to the requirement for Catawba. This requirement is loosely based on

. Specification 4.8.1.1.2a.4 (1E Diesels), but considers that the SSF Diesels are manual start only, and not subject to.a test frequency based on successful starts, b.

Requirements for new fuel being added to the tank are virtually identical to those'of the 1E Diesels.

c.- Manufacturer-recommended 18-month inspection requirement is similar to that for 1E Diesels, except that in view of the redundant nature of the SSS function, plant shutdown is not required.

'4.7.14.2 Surveillance requirements for SSS diesel starting batteries are similar to those for IE Diesels, but reficct the fact that the batteries are nickel-cadmium and, therefore, criteria for specific gravity and eletrolyte level are not applicable.

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-3 4.7.14.3

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The specification to verify operability of the Standby Makeup Pump a.

water supply is-based on the Catawba specification, except that the calter'nate-water supply of 112,320 gallons has been replaced by the 1 Refueling Water Storage Tank (RWST). The RWST is verified weekly.

(per T/S. 3/4.5.5) to contain at least 372,100 gallons of water

" borated to a concentration between 2,000 and 2,100. PPM.

b.

As noted previously,-the flow rate of 26 GPM is based upon the total of allowed leakage (Identified and unidentified) and reactor coolant pump seal leakoff. The required pressure is equal to the pressurizer safety set point of 2485 psig..According to the pump manufacturer, the pump can deliver 26 GPM at 2735 psig.

"4.7.14.4 The specifications for surve111snee of 250/125 Volt Battery Bank are based on those for the 1E Diesel batteries, although the surveillance is performed less frequently. This relaxed frequency is consistent with the probability that the batteries will-be required.

4.7.14.5 The Steam Turbine Auxiliary Feedwater pump is determined operable per

. Tech Spec 4.7.1.2a.

Specification 4.7.14.5 assures that a source of steam is available through valve SA48ABC, which fails open on deenergization of the "C" solenoid.

4.7.14.6 The instrumentation surveillance requirements are consistent with speci-fications 3.3.3.5 and 3.3.3.6.

B. - Significant Hazards Considerations Analysis

.This analysis is provided to determine whether the proposed amendment involves a significant hazards-consideration, as defined by 10CFR50.92.

The proposed Technical Specification will not incrcase the probability of an

' accident occurring, either one previously evaluated or not, because the SSS is used to mitigate events which are already in progress, and because the equip-

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ment upon which surveillance is performed is not directly associated with equipment whose failure would cause an accident.

Inoperability of the SSS could reduce the capability to mitigate the conse-quences of an event which disables the normal and emergency shutdown systems, and-renders the control room uninhabitable. Therefore, controls on the in-operability of the 'SSS, and formalized surveillance procedures, are expected to contribute to a net decrease in potential probability of an accident.

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The'_ Federal R'gister Notice which-published the interim final rule contained e

examples of amendments that:are not likely to involve significant'hhzards considerations. 'One example was a change that constitutes additional limita-tions, restrictions, or controls not presently included in the Technical Specifications.

The prcposed' Technical Specification does not reduce or affect any marb n of i

safety, except-as noted above with respect to a potential decrease in conse-quences to the public.

Based on the above, Duke Power Company concludes that the proposed amendment

.does not involve a significant. hazards consideration.

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