Text

Amends 65 & 57 to Licenses DPR-31 & DPR-41,respectively, Revising Tech Specs to Clarify Term Operable Re Single Failure Criterion for Safety Sys in Power Reactors.Update of Organization Chart Encl
	ML17340B203
Person / Time
Site:	Turkey Point
Issue date:	05/12/1981
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17340B204	List: ML17340B203; ML17340B205; ML17340B206;
References
	NUDOCS 8105180048
	Download: ML17340B203 (55)
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UNITED ST%: -"s NUCLFAR R GULATGRY CGfv':iVilSSIGN

'LVASHINGTOk.O. C. 2CSss FLORIDA POWER'AHD L'tGHT COVPE'HY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT HO.

3 R<EHDt1ENT TO FACILITY OPERATING LICENSE Amendment No. 66 License Ho.

DPR-31 1.

The Nuclear Regulatory Commission (the Commission) has found tgat:

A.

The applications for amendment by Florida Power and Light Company (the licensee) dated September 12, 1980 and March 10,

1981, comply with the standards and requirements of the Atomic Energy Act of

1954, as amended (the Act) and the Commission-'s..rules and regula-tions 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 (i) that the activities authori:ed by this amendment

."=-;" be c"nducted without endangering the heal-.h and safety of the

.- '1'.c, and (ii) that such activities will be conducted in comp]

ance w;zh :he Cori-.,i'sicn's regulations; D.

The issuanc of this

=;.enc-ent will no.

be inimical "o the cor;; on de ense ard securi y cr to the heal h and safe:y of the public; and E.

The issuance of this amendment is in accordance wi:h 10 CFR Par.

51 of the Comnission's regulations and all applicable req"irements have been satis ied-

2.

Accordinoly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendme'nt, and paragraph 3.B of Facility Operating License t<o.

DPR-31 is hereby amended to read as follows:

(B)

Technical Specifications The Technical Specifications contained in Aooendi ces A and B, as revised through Amendment Ho.

6~, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specificat,ions.

I 3.

This license amendment is ef ective as of the date of its issuance.

FOR TPE

hUCLEA, REGULATORY COtNI SSION'ttachment:

Changes to the Technical Specifications Date of Issuance:

May 12, lg81 I

even ~.Narg a j Operating Reactor Division of Licens ief Br anch

."'1 g

I g cc~V

~ (L 1

Cg

~8+rC NUCI ""AR R:-GULATORY COViiV(lSSlON

'Ls'ASHlMGTOV, D. C. 20555 FLORIDA PO>iER AND LIG,'-~T COMPANY DOCYET HO.53-251 4

TURKEY POINT PLANT UNIT I'. 4 AHENDMEHT TO FACILITY OPERATING LICENSE Amendment Ho.

5g License No.

DPR-41 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The applica ions for amendment by Florida Power and Lioht Company (the licensee) dated September 12, 1980 and March 10,

1981, comply with the standards and requirements o, the Atomic Energy Act of

1954, as amended (the Act) and the Commission's rules and regula-tions set forth in 10 CFR Chapter I; B.

The facilitv will operate in conformity with the applications, the provisions o

the Act, and the rules. and regulations of the Commission; C-There is reasonable assurance (i) that the activities authorized by this amendmen.

ca" be conducted without endangeri no the health and safety o

the bl:c, and (ii) that such activities will be conducted in ccmpl-:=-,"ce w-;=h.he Corn sston's regula ions; D.

The issuance o, this a;..en='.-,.e.".t will not be inimical.o the cormn defense and security or tc -.he health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Par.

51 of the Conmission's regulations and all applicable requirements have been satisfied.

2-2.

Accordingly, the license is amended by changes to the Technical Specifiqations as indica.ed in the attachment to this license amendment, and paragraph 3.B oi Facility Operating License No.

DPR-41 is hereby amended to read as follows:

(B)

Technical S ecifications The Technical Speci ications contained in Appendices A and B, as revised through Amendment No. 57, are hereby incorporated in the 1',cense.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is e fective as o

the date of its issuance.

FO THE NUCLEAR

~GULATORY CO/i'iISSION l@<~~ P.

Steven A. Varaa 5h 1 Operating Reactors B

Division of Licens T

anch gl At.achment:

Changes to the Technical Specifications Date of Issuance:

May 12, 1981

ATTACHMENT TO LICEf~S AffEflDlfEHTS AY>EffDfiEffTi!0.

65 TO FACILiTY OPERATING LICENSE HO.

DPR-31 Af'i HDtlEflT HO.

57 TO FACILITY OPERATING LIC USE fl0.

D. R-41 DOCKET NOS.

50-250 AHD 50-251 Revise Appendix A as follows:

~R Insert Paaes 3.1-1

3. 3-1 3.4-2

3. 4-3 3.4 4

3. 4-5

3. 4-6

3. 5-1

3. 6-2

3. 7-1 3.7-2 3.13-1 3.1 5-1

3. 0-1 83.0-1 83.0-2 3.1-1

3. 3-1

3. 4-2

3. 4-3

3. 4-4

3. 4-5

3. 4-6

3. 5-1

3. 6-2

3. 7-1

3. 7-2

3. 13-1

3. 15-1 6-1 0-3

Re..ave Paoes ense",4 Pa es 6-7 6-7 6-8 6-9 6-8 6-9 6-10 6-16 6-10 6-15,

I

'P

1. 0 DEFI NITIONS The definitions used for these specifications follow.

l. 1 SAFETY LIHITS Safety limits are the necessary quantitative restrictions placed upon those process variables that must be controlled in order to reasonably protect the integrity of certain of the physical barriers which guard against the uncontrolled release of radioactivity.

If any safety limit is exceeded, the associated reactor shall be shut down until the AEC authorizes resumption of operation.

1.2 LIHITING SAFETY SYSTEH SETTINGS Limiting safety system settings are set points for automatic protective devices responsive to the variables on which safety limits have been placed.

These set points are so chosen that automatic protective actions will correct the most severe, anticipated abnormal situation so that a safety limit is not exceeded.

1.3 LIHITING CONDITIONS FOR OPERATION Limiting conditions for operation are those restrictions on reactor operation, resulting from equipment performance capability, that must be enforced to ensure safe operation of the facility.

1.4 OPERABLE - OPERABILITY A system, subsystem, train, ccmponent or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation,

controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, ccmponent or device to perform its function(s) are also capable of performing their related support function(s).

Amendments 65 8

57

l

3-0 LIMITING CONDITIONS FOR OPERATION Appl icabil ity 3.0.1 If one of the below listed limiting conditions for operation can not be satisfied because fewer components are operable than are required, the unit shall be placed in hot shutdown within eight hours and cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months unless appropriate corrective action is taken before the time expires-This specification applies only to specifications 3.3.1,3.4.1.b,3.4.2-b,3.4.3.b,3.4.4.b,3.4.5.b,3.5,3.6.d, 3.7.2 and 3.13.3.

3.0.2 For purposes of determining if a ccmponent is operable for LCO considerations, the component need not be considered inoperable due to inoperability of its normal or emergency power supply if all of its redundant components are operable with their normal or emergency power supplies operable.

Amendments 65 8

57

3. 0-1

83.0 BASES FOR LIHITING COND'ITIONS'OR OPERATION, APPLICABILITY 3.0.1.

This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements and whose occurrence would violate the intent of the specification.

For example, Specification 3-4. 1 requires each Reactor Coolant System accumulator to be OPERABLE and provides explicit ACTION requirements if one accumulator is inoperable.

Under the terms of Specification 3.0.1, if more than one accumulator is inoperable, the unit is required to be in at least HOT SHUTOOMN within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

As a further example, Specificafion 3.4.2.a requires two Contairment Spray Systems to be OPERABLE and provides explicit ACTION requirements if one spray system is inoperable:

Under the terms of Specification 3.0. 1, if both of the required Containment Spray Systems are inoperable, the unit is requi red to be in at least HOT SHUTOOWN within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months and in at least COLO SHUTDOMN in the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

It is assumed that the unit is brought to the required condition within the, required times by promptly*initiating and carrying out the appropriate ACTION statement.

3.0.2 This specification delineates what additional conditions must be satisfi ed to permit operation to continue, consistent with the ACTION statements for power sources, when a normal or emergency power source is not OPERABLE.

It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem,

train, ccmponent or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statenents associated with individual systems, subsystems,

trains, components, or devices to be consistent with the ACTION statements of the associated electrical power source-It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting Condition 'for Operation for the normal or emergency

Promptly means one hour to act and six.hours to hot shutdown.

Amendments 65 5 57 B3.0-1

)1

power source, not the individual ACTION statements for each system subsystem, train, component or device that is determined to be inoperable solely because of the inoperability of its normal or emergency power source.

For example, Specification 3.7. 1 requi res in part that two emergency diesel generators be OPERABLE.

The ACTION statement provides for an out-of-service time when one emergency diesel generator is not OPERABLE-If the definition of OPERABLE were applied without consideration of Specification 3.0.2, all systems subsystems,

trains, components and devices supplied by. the inoperable emergency power source would also be inoperable.

This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation.

However, the provisions of Specification 3-0.2 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator

instead, provided the other specified conditions are satisfied.

In this case this would f

mean that the corresponding normal po~er source must be

OPERABLE, and al 1 redundant

systems, subsystems,

trains, ccmponents, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.2 (i.e.,

be capable of performing their design function and have at least one norma) or one emergency power source OPERABLE}. If they are not satisfied, shutdown is required in accordance with this specification.

In cold shutdown or refueling condition Specification 3.0.2 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these conditions must be adhered to.

Amendments 65 5 57 B3.0-2

A 1

3.1 REACTOR COOLANT SYSTE/1

~pli Pill:

Appll 0

0 l 0 0

0 0

0 1

0

~0b ective:

To specify those limiting conditions for operation of the Reactor Coolant System which must be met to assure safe reactor operation.

0 A

0 0

0 a.

Reactor Coolant Pum s

l.

A minimum of ONE pump shall be in operation when the reactor is in power operation, except during low power physics tests..

2.

A minimum of ONE pump, or ONE Residual Heat Removal Pump, shall be in operation during reactor coolant boron concentration reduction.

3.

Reactor power shall not exceed 10$ of rated power unless at least Tbl0 reactor coolant pumps are in operation.

4.

Reactor power shall not exceed 45$ of rated power with only two pumps in operation unless the overtemperature hT trip setpoint, Kl, for two loop operation, has been set at 0.88.

5.

A reactor coolant pump shall not be started when cold leg temper ature is ( 275'F unless steam generator secondary water temperature is less than 50'F above the RCS temperature (including instrument error).

b.

Steam Generators 1.

A minimum of TMO steam generators shall be operable when the average coolant temperature is above 350F.

C.

Pressurizer Safety Valves l.

ONE valve shall be operable whenever the head is on the reactor vessel except during hydrostatic test.

2.

THREE valves shall be operable when the reactor

,coolant average temperature is above 350F or the reactor is critical.

Amendments 65

8. 57

3. 1-1

3.3 CONTAINiiiENT

~pfi TTT:

Ap Tf <<A T

f f

A Objective:

To define the operating status of the containment.

~if i f:CPNTAT MENT T

ENN T

1.

The contairment integrity {as defined in 1.5) shall not be violated unless the reactor is in the cold shutdown condition-Speci fication 3.0.1 applies to 3.3.1.

2.

The contairment integrity shall not be violated when the reactor vessel head is removed unless the reactor is in the refueling shutdown condi tion.

INTERNAL PRESSURE If the internal pressure exceeds 3 psig or the internal vacuum exceeds 2 psig, the condition shall be corrected within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or the reactor shall be brought to hot shutdown.

Amendments 65 8

57 3.3-1

5.

TMO residual heat removal pumps shall be'operable-6.

TWO residual heat exchangers shall be operable.

7.

All valves, interlocks and piping associated with the above components and required for post accident operation, shall be operable, except valves that are positioned and locked.

Valves 864-A, B; 862-A, 8; 865-A, B, C; 866-A, B shall have power removed free their motor operators by locking open the circuit, breakers at the Motor Control Centers.

The air supply to valve 758 shall be shut off to the valve operator.

b.

During power operation, the requirements of 3.4. la may be modified to a11ow one of the following components to be inoperable (including associated valves and piping) at any one time except for the cases stated in 3.4. l.b.2.

If the system is not restored to meet the requirements of 3.4. 1a within the time period specified, the reactor shall be placed in the hot shutdown condition.

If the requiraaents of 3.4. la are not satisfied within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the reactor shall be placed in the cold shutdown condition.

Specification 3.0.1 applies to 3.4.1.b.

l.

ONE accumulator.

may be out of service for a period of up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2.

ONE of FOUR safety injection pumps may be out of service for 30 days-A second safety injection pump may be out of service, provided the pump is restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

TWO of the FOUR safety injection pumps shall be tested to demonstrate operability before initiating maintenance of the inoperable pumps.

3.

ONE channel of heat tracing on the flow path may be out of service for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , Amendments 65 5 57 3.4-2

0 C

5.

ONE residual heat exchanger may be out of service for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6..

Any valve in the system may be inoperable provided repairs are completed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Prior to

'nitiating maintenance, all valves that provide the duplicate function shall be tested to demonstrate operability.

2.

BlERGENCY CONTAINMENT COOLING SYSTEMS k

a.

The reactor shall not be made critical, except for low power physics tests, unless the following conditions are met:

1-THREE emergency contairroent cooling units are operable.

2-TWO contairment spray pumps are operable.

3.

All valves and pipi ng associated with the above ccmponents, and required for post accident operation, are operable.

b.

Our ing power operation, the requi rements of 3.4.2a may be modified to allow one of the following components to be inoperable (including associated valves and piping) at any one time.

If the system is not restored to-meet the requirements of 3.4.2a within the time period specified, the reactor shall be placed in the hot shutdown condition.

!f the requirements of 3.4.2a are not satisfi ed within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the reactor shall be placed in the cold shutdown condition.

Specification 3.0,1 applies to 3.4.2.b.

Amendments 65 8

57

3. 4-3

e

1-OE HE emergency contairment cooling unit may be out of service for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Prior to initiating maintenance the other TWO units shall be tested to-demonstrate oper ability.

2.

ONE contairment spray pump may be out of service hours.

provided it is restored to operable status with 24 ln urs.

The rema>ning contairment spr ay pump shall be tested to demonstrate operability before initiating maintenance on the inoperable pump.

3.

Any valve in the system may be inoperable provided repairs are ccmpleted within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Prior to initiating repairs, all valves that provide the duplicate function shall be tested to demonstrate operability.

3 e EMERGENCY COHTAINi lE NT FILTERING SYSTEM a.

The reactor shall not be made critical, except for low power physics tests unless:

1.

THREE emergency contairment filtering units are operable-2.

All valves, interlocks and piping associated with the above components and required for post-accident operation, are operable.

b.

During power operation:

C 1.

OHE unit may be inoperable for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if the other Tl<0 are operable.

2.

Any valve in the system may be inoperable provided repairs are completed within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s-Prior to initiating maintenance, all valves that provide the duplicate function shall be tested to demonstrate operability.

3.

Specification 3.0. 1 appl'ies to 3.4.3.b.

4.

COMPONENT COOLING SYSTEM a.

The reactor shall not be made critical except f 1

p p ysics tests, unless the following conditions ar' ower h

ep or ow met:

Amendments 65

& 57 3 ~ 4 4

4 1.

THREE canponent cooling pumps are operable.

20 3.

THREE component cooling heat exchangers are operable.

All valves, interlocks and piping associated with the above components are operable.

b.

During power operation, the requirements of 3.4.4a may be mo ified as stated below-If the system is not restored to meet the conditions of 3.4.4a within the time period specified, the reactor shall be placed in the hot shutdown condition.

If the requi rements of 3.4.4a are not satisfied within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor shall be placed in the cold shutdown condition.

Specification 3.0. 1 applies to 3.4.4.b.

1.

ONE pump may be out of service for 7 days.

2.

ONE additional pump and ONE heat exchanger may be out of service for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

INTAKE COOLING WATER SYSTEM a.

The reactor shall not be made critical unless the following conditions are met:

1.

THREE intake cooling water pumps and TWO headers are operable.

2.

All valves, interlocks and piping associated with the operation of these

pumps, and required for post accident operation, are operable.

Amendments 65 5 57

3. 4-5

b.

During power operation, the requirements of 3.4.5...

a ove, may be modified to allow any one of the following components to be inoperable provided the remaining systems are in continuous operation.

Ef the system is not restored to meet the requirements of 3.4.5.a.

within the time period specified, the reactor shall be placed in the hot shutdown condition.

If the requirements of 3.4.5. a.

are not satisfied within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor shall be placed in the cold shutdown condition, Specification 3.0. 1 applies to 3.4.5.b.

1.

One of the two headers may be out of service for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2-One intake cooling water pump may be out of service for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Amendments 65

& 57

3. 4-6

1 1

It r

~

3. 5 INSTRUNEI'/TATION

~A1i bi Objective:

Applies to reactor and safety features instrumentation systems.

To delineate the conditions of the instrumentation and safety circuits necessary to ensure reactor safety.

Tables 3.5-1 through 3-5-4 state the minimum instrumentation operating conditions.

Specification 3.0. 1 applies to Tables 3.5-1 through 3.5-3.

Amendments 65 8

57 3.5-1

1.

TMO associated charging pumps shall be operable.

2.

THREE boric acid transfer pumps shall be operable.

3.

The boric acid tanks together shall contain a minimum of 6160 gallons of a 20,000 to 22,500 ppm boron solution at a temperature of at least 145F.

4.

System piping, interlocks and valves shall be operable to the extent of establishing one flow path frcm the boric acid tanks, and one flow path frcm the refueling water storage tank, to each Reactor Coolant System.

5.

TWO channels of heat tracing shall be operable for the flow path from the boric acid tanks.

6.

The primary water storage tank contains not less than 30,000 gallons of water.

d.

During power operation, the requirements of 3. 6.b and c

may be modified to allow one of the following canponents to be inoperable.

If the system is not restored to meet the requi rements of 3.6b and c within the time period specified, the reactor(s) shall be placed in the hot shutdown condition.

If the requirements of 3.6.b and c

are not satisfied within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor(s) shall be placed in the cold shutdown condition.

Specification 3.0. 1 applies to 3.6.d.

1.

One of the two operable charging pumps may be removed from service provided that it is restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

One boric acid transfer pump may be out of service provided that it is restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

One channel of heat tracing may be out of service for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Amendments 65

& 57

3. 6-2

30 7 ELECTRICAL SYSTEMS

~A1i bill:

A 1i <<h i1 ill<<1 i

1 p

for the operation of auxiliaries.

To define those conditions of electrical pow'er availablity necessary (1) to provide for safe reactor operation, and (2) to provide for the continuing availability of engineered safety features.

L Bh h11 b *<<

f cold shutdown without:

a.

The associated 239 KY-4160 volt start-up transformer in service.

b.

4160-volt busses A and 8 of the associated unit, and either bus A or 8 of the second unit, energi zed.

c.

THREE out of FOUR 480-volt load centers and 480-volt motor control centers A,

8 or C,

and D of the associated unit energized.

d.

Tl!0 diesel generators operable with on site supply of 40,000 gallons of fuel available.

e.

Four batteries and associated DC systems are operable with FOUR out of SIX battery chargers operable.

2.

During power operation or restarting from hot shutdown the following components may be inoperable:

a.

ONE start-up transformer may be out of service provided both diesel generators are operable.

The NRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and be advised of plans to restore the transformer to service.

Amendments 65 8

57 3.7-1

b.

Power operation may conti'nue if ONE diesel generator is out of service provided (1) the remaining diesel generator is tested daily and its associated engineered safety features are operable, and (2) either start-up transformer is operable.

If the diesel outage is to be seven (7) days or more the NRC shall be notified.

c.

ONE battery may be out of service for a period of twenty four hours.

d-Specification 3.0. 1 applies to 3.7.2.

Amendments 65 '5 57 307-2

i C

\\

3.13 SHOCK SUPPRESSORS SNUB8ERS

~dfi Pfll: Apll <<1 p

1 1*

<<f related pipe restraints (snubbers).

Objective:

To define the limiting conditions for operation applied to the operability of safety-related snubbers.

~if': l.

1 11 f

p 1

p ld Shutdown and Refueling Shutdown, all (safety-related) snubbers listed in Table 3. 13-1 shall be operable except as noted in 3.13.2 through 3.13.4 below.

2.

Frcm the time that a snubber is determined to be inoperable, continued reactor operation is permissible only during the succeeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months unless the snubber is sooner made operable or replaced with an operable snubber.-

3.

If the requirements of 3.13. 1 and 3. 13.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Specification,3.0.

1 applies to 3.13.3.

4.

If a hydraulic snubber is determined to be inoperable while the reactor is in the cold shutdown mode or the refueling mode, the snubber shall be made operable or replaced with an operable snubber prior to reactor startup.

5.

Snubbers may be added to Table 3. 13-1 without prior license amendment provided that a

revision to Table 3.13-1 is included with a license amendment request within 60 days.

Amendments 65 8

57

3. 13-1

y*e

3. 15 OVERPRESSURE MITIGATING SYSTEM

~hgi lll:

E hll*h p l gill<<l <<h<<h fig f

10 CFR 50, Appendix G, are not exceeded.

~pp To minimize the possibility of an overpressure transient which could exceed the limits of 10 CFR 50, Appendix G.

1.

At RCS temperature less than or equal to 380'F, valves MOV-*-843 A, MOV-*-843 8, NOV-*-866 A, and MOV-*-866 8 shall be closed.

2.

If any of the valves in 3. 15. 1 are found to be open while

]

RCS temperature is less than or equal to 380'F, perform at least one of the following within the next 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s:

'a 4

b.

c ~

block the corresponding flow path to the reactor

vessel, h

close the valve, or depressurize and vent the RCS through an opening with an area of at least 2.20 square inches, or verify at least one pressurizer power operated relief valve is maintained open.

3.

At RCS temperature less than or equal to 275 F, two pressurizer power operated relief valves shall be operable at the low setpoint range.

a.

If one power operated relief valve is inoperable with RCS temperature less than or equal to 275'F, perform at least one of the following within 7 days:

(1) restore operability of the power operated relief valve, or (2) depressurize and vent the RCS through an opening with an area of at least 2.20 square inches, or (3) verify at least one pressurizer power operated relief valve is maintained open.

b.

If both power operated relief valves are inoperable with RCS temperature less than or equal to 275'F, perform at least one of the following within the next 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

(1) restore operability of at least one power operated relief valve, or (2) depressurize and vent the RCS through an opening with an area of at least 2.20 square inches, or (3) verify at least one pressurizer power operated relief valve is maintained open.

Amendments 65 8

57 3.15-1

6.0 AOHINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager - Nuclear shall be responsible for overall licensed facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 OFFSITE The offsite organization for facility management and technical support shall be shown on Figure 6.2-1.

6.2.2 FACILITY STAFF The Facility organization shall be as shown on Figure 6.2-2 and:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shcwn in Table 6.2-1.

b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

cd At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery frcm reactor trips.

6-1 Amendments 65 8

57

EXECUTIVE TICE PRESIDENT Qo v) ~

m QC C

lA DIRECTOR NUCLEAR AFFAIRS VICE PRESIDENT ADYANCED SYSTEHS AND TECHNOLOGY DIRECTOR EMY I RDHMasv7u.

AFFAIRS MANAGER OWER RESOURCE NUCLEAR TICE PRESIDENT.

POWER RESOURCES MANAGER PORER RESOURCES SERTICES TICE PRESIDENT FUEL RESOURCES 6

CORPORATE DEYEI.OPHENT HAHAGER NUCLEAR ANALYSIS COMPANY NUCLEAR REYIEW BOARD TICE PRESIDENT EMGIMEERIMC.PROIEC'IS S

CONSTRUCTION MANAGER NUCLEAR LICENSIMC MANACER DUALITY ASSURANCE HANAGER POKER RESOURCES NUCLEAR SERVICES CHIEF ENGINEER POWER PLANT ENGINEERING SITE

~ MAMACER lN POWER RESOURCES Sl'AFF NUCLEAR SEE FIGURE 6.2 2 CONTINUED ON FIGURE 6.2-2

'0 INCIUDES HEALTH PHYSICS RAOIOCHOIISTR'Y, PLANT SUPPORT, FIRE PROTECTION ADMINISTRATOR, EHERGEHCY PLANNING, ETC.

FIGURE 6.2-I OFFSITE ORGANIZATION FOR FACILITY HANAGEHENT AND TECHNICAL SVPPORT'

PO'i';2 B=-SOURCES STA?r tiEAL..'i PHYSICS AEFFA TO FIG. 6.2-1 1

1 I

rONER RESOURCES STAFF FIRE PROTECTION ADHItlISTBATOR REFER TO FIG. 6.2-1 OPERATIONS SUPER IhiTENDLHT NUCLEAR' FOSSIL PL'LHT QUALITY CONTROL SUPERVISOR SITE HAttAGER PLANT NAHAGER NUCLEAR TECJJNICAL DEPARTHENT SUPERVISOR PLANT SECURITY SUPERVISOR PLANT

'JCLEAR SAFETY CO 2JITTEE flAIHTENAltCE SVPERINTENDEHT NUCLEAR ilFAJ.Til l'liYSICS

"-IEBVISOR CIIE11ISTAY SUPERVISOR OPERilTIOHS SUPERVISOR REACTOR SUPERVISOR TRAINING SUPERVISOR SHIFT TECHNICAL ADVISOR INSTAUHENT CONTROL SUPERVISOR ASSISTANT SUPERI NT?NDENT HECHA!JICAL NAINTENANCE RJC LEAR ASS ISTliN1 SVPEAINTEHDE;itT EL?A:TRICAL MAItlTENANCE hVCLEAR I'JiDIATIO:l PiiOTECTIOtl 11Lill NUCLEAR PLANT SUPERVISOR tlUCLEAR MATCH ENGIJJEER 1 - SENIOR OPE?A vR LICENSE 2

G AS SH b".t iN TAE

c. 6 ~ 2-1 NUCLEAR CONTROL CENTER OPERATOR PLMiT CRGANIEAT:Gti C:-~:-.T FIGURE 6.2-2 Vill.ICEHSED OPERATORS

)

I

~

C 6.4.2 A training program for the Fire Emergency. response members shall be maintained under the direction of the Fire Protection Administrator and should meet" or exceed, the requirements of Section 27 of the NFPA Code-1975, except for fire Brigade training sessions which shall be held at least quarterly.

6.5 6.5.1 REVIEW AND AUDIT Plant Nuclear Safety Committee (PNSC)

6. 5.1.1 FUNCTION The PNSC shall function to advise the Plant Manager-Nuclear on all matters related to nuclear saf ety.

6 ~ 5. 1 ~ 2 COiMPOS ITION The Plant Nuclear Safety Committee shall be composed of the:

1.

Chairman:

Plant Manager Nuclear 2.

Vice Chairman:

Operations Superintendent - Nuclear 3.

Technical Depar tment Supervisor 4.

Maintenance Superintendent Nuclear 5.

Instrument and Control Supervisor 6.

Health Physics Supervisor 7.

Reactor Supervisor 6 ~ 5.1. 3 ALTERNATES Alternate members shall be appointed in writing by the PNSC Chairman to serve on a temporary basis;

however, no more than two alternates shall participate in PNSC activities at any one

, time.

6'.1

~ 4 MEETING FRE UENCY The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman.

Amendments 65 8

57 6-6

)

6. 5. 1. 5 QUORUH A quorum of the PNSC shall consist of the Chairman or Vice Chairman and four (4) members including alternates.

6. 5.1.6 RESPONSIBILITIES The Plant Nuclear Safety Committee shall be responsible for:

a.

Review of 1) all procedures and changes thereto required by Section 6.8 and 2) any other proposed procedures

'or changes.

thereto as determined by the Plant Hanager - Nuclear to affect nuclear safety.

b.

co d.

e.

Review of all proposed tests and experiments that affect nuclear safety.

Review of all proposed changes to the Technical Specifications in Appendix A of the license.

Review of all proposed changes or modifications to plant systems or equipment. that affect nuclear safety.

Investigation of all violations of the Technical Specifications and preparation and forwarding a report covering evaluation and recommendations to prevent recurrence to the Hanager of Power Resources

- Nuclear, to the Vice President of Power Resources a'nd to the Chairman of the Company Nuclear Review Board.

Amendments 65 5 57

'-7

t J

f.

Review of facility operations to detect potential safety hazards.

g.

Perfonnance of special reviews and investigations and reports thereon as requested by the Chairman of the Company Nuclear Review Board.

h.

Review of the Plant Security Plan and implementing procedures and submitting reccmmended changes to the Chairman of the Company Nuclear Review Board.

i.

Review of the Emergency Plan and implementing procedures and submitting recommended changes to the Chariman of the Company Nuclear Review Board.

6. 5.1. 7 AUTHORITY The Plant Nuclear Safety Committee shall:

a.

Recommend to the Plant iNanager - Nuclear written approval or disapproval (in minutes of PNSC meeting) of items considered under 6.5.1.6(a) through (d) above.

b.

Render determinations in writing (in minutes of PNSC meetings) with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide immediate written notification to the Vice President

- Power Resources and the Company Nuclear Review Board of disagreement Amendments 65 8

57 6-8

between the PNSC and the Plant Manager Nuclear; however, the Plant Manager Nuclear shall have responsibility for resolution of such disagreements pursuant to 6-1.1 above-6.5.1.8 RECORDS The Plant Nuclear Safety Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Power Resources and Chairman of the Company Review Hoard.

6 ~ 5. 2 COMPANY NUCLEAR REVIEW BOARD C'ORB 6 2.1 FUNCTION The Company Nuclear Review Hoard shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant operations.

b.

Nuclear engineering.

c.

Chemistry and radiochemistry.

d.

Metallurgy.

e.

Instrumentation and control Radiological safety.

g.

Mechanical and electrical engineering'.

Quality assurance practices.

6'.2.2 COMPOSITION The CNRB shall be commposed of the:

Amendments 65 5 57 6-9

l ~

1-Chairman:

Vice President - Advanced Systems and Technology

6. 5.2.3 2.

Member:

Chief Engineer Power Plant Engineering 3.

Member:

Vice President Power Resources 4-Member:

Manager of Power Resources Nuclear 5.

Member:

Director of Nuclear Affairs 6-Member:

Power Plant Engineering Manager 7-Member:

Power Plant Engineering supervisor ALTERNATES Alternate members shall be appointed in writing by the (CNRB) Chairman to serve on a temporary basis;

however, no more than two alternates shall participate in (C1LB) activities at any one time.

6. 5. 2.4 CONSULTANTS Consultants shall be utilized as'determined by the CNRB to provide expert advice to the. CNRB.

6.5. 2.5 MEETXNG FRE UENCY The CNRB shall meet at least once per calendar quarter during the intial year of facility operation following fuel loading and at least once per six months thereaf ter.

6.5.2.6 UORUM A quorum of the CNRB shall consist of the Chariman or designated acting Chariman and four (4) members including alternates.

No more Amendments 65 5 57 6-1 0

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PNSC and approved by the Plant >fanager Nuclear prior to implementation and periodically as provided by procedure.

6.8. 3.

Temporary changes to procedures of 6.8.1 above may be made p rovided:

a.

The intent of the original procedure is not altered

~

b.

The change is approved by two members of the plant management staff, at least one of shorn holds a Senior Operators License on the unit affected.

c ~

The change is documented, reviewed by the PNSC and approved by the Plant Manager - Nuclear within fourteen days of imp 1emen ta tion 6-1 5 Amendments 65 5 57

)

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C' J

ML17340B203

Text

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