Text

Amend 47 to License NPF-47,modifying Tech Specs 3.0.4,4.0.3 & 4.0.4,per Generic Ltr 87-09 & Making Editorial Corrections to Three Tech Specs
	ML20059F383
Person / Time
Site:	River Bend
Issue date:	08/31/1990
From:	Charemagne Grimes; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20059F388	List: ML20059F383; ML20059F396;
References
	GL-87-09, GL-87-9, NUDOCS 9009110198
	Download: ML20059F383 (92)
	v • d • e

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es UNITED STATES

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4 NUCLEAR REGULATORY COMMISSION ~

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1 GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 l

RIVER BEND STATION. UNIT 1

. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No'. 47

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License No. NPF-47 1.

The Nuclear-Regulatory. A maission (the Comission) has found that:

A.

The application for amendment by Gulf States Utilities Company j

-(the licensee): dated September 30 1988, and supplemented by two l

~etters dated June.6,-1990, and letters dated June 26, 1990, and' l

August 22, 1990, complies with the standards and requirements l

of the Atomic Energy Act of 1954, as amended (the Act), and tha-Commission's rules ~and regulations set forth in 10 CFR ',hapter I; 8.

The facility will operate in conformity with-the' app'ication, as E

amended, the provisions of the Act, and the rules a'id regulations H

of the Commission; l'

a h

C.

There is reasonable assurancer (1) that-the activities authorized by this amendment can be conducted without endangering the health.

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and safety of the public, and (ii) Lthat such activities,will be -

L-conducted in compliance with the Commission's regulations; q

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D.

The issuance of this license amendment will not be inimical to the 3

common defense and security or to the' health and safety of the public; '

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.and j

q The issuance of this amendaient is in acccrdance with 10 CFR Part 51

.E.. 'of the Commission's regulations and all applicable requirements have.-

been satisfied.'

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Accordingly, the license is amended by changes to the Technical

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. Specifications as indicated in-the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby i

amended to read as fo11ov4:"

(2) Technical Specifications and Environmental Protection Plan The Technical Sr:mifications contained in Appendix' A, as revised through Amendmenc No. 47 and the Environmental Protection Plan contained in Appendix 8 - are hereby incorporated 'in the license.

GSU shall operate the facility in accordance with the Technical 3

Specifications and the Environmental-Protection Plan.

1

- 3.

The license amendment is effective immediately and is'.to be implemented no later than-September-29 1990.

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FOR THE NUCLEAR REGULATORY COMMISSION L

l 1.

IJ (JM L

Christopher I. Grimes, DirJetor L

Project Directorate IV-2 l'

Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

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Attachment:

Changes to the Technical y

Specifications

, DateofIIssuance: August 31, 1990 li '

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.-r ATTACHMENT TO LICF.NSE AMENDMENT NO. 47-FACILITY OPERATING LICENSE NO. NPF-47 h

DOCKET NO. 50-458 Replace the following page of the Appendix "A" Technical Specifications with-

'the enclosed page.

The revised page is identified by Amendment number and contains a vertical line indicating the area of change.

The-overleaf pages

are provided to maintain-document completeness.

L REMOVE-INSERT 3/4 0-1 3/4 0-1 3/4 0-2

.3/4 0-2 3/4 l'4 3/4 1-4 3/4 1-7 3/4 1-7 3/4 1 3/4 1-10 3/4 1 3/4 1-11 3/4 1-12 3/4 1-12 3/4 1-13 3/4 1-13 3/4 3 3/4 3-1 3/4 3-10 3/4 3-10 gs 3/4 3-61 3/4 3-61 3/4 3-65 3/4 3-65 3/4.3-68 3/4 3-68 3/4 3-70 3/4 3,

3/4 3-73 3/4 3-73 3/4 3-87 3/4 3-87 3/4 3-93

-3/4 3-93 1

3/4 3-94 3/4 3-94 3/4 3-99

'3/4 3-99 3/4 3-109 3/4 3 109

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'3/4 4-27 3/4 4-27.

s 3/4 4-29 3/4 4-29 3/4 5-9 3/4 5-9

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3/4 6-8 3/4 6,

3/4 6-9 3/4 6-9 3/4 6-20 3/4 6-20 3/4 6-31 3/4 6-31 0ll u'.

3/4 6-51 3/4 6-51 3/4 7-21' 3/4'7-21 3/4 7-23 3/4 7-23 5" -

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3/4-7-28 3/4 7-28 W

3/4 7-30 3/4 7-30' 5,

3/4 7-35 3/4 7-35 L !f 3/4 8-25 3/4 8-25

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3/4 8-33 3/4 8-33 q.

W 3/4 9-18 3/4 9-18

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3/4 11-4' 3/4 11-4 3/4-11-5 3/4 11-5 3/4 11-11 3/4 11-11

'3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4 11-14.

3/4'11-14 t

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'3/4 11-18 3/4 11>18

-3/4 12-2 3/4 12-2 I

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83/4 0-2 B3/4 0-2 B3/4 0-3 83/4 0-3 B3/4 0-4 83/4 0-5 I~

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3/4.0 APPLICABILITY

$ LIMITING' CONDITION FOR OPERATION

-3.0.1: Compliance with the Limitiag Conditions for Operation contained in the-succeeding Specifications-is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met..

3.0.2; Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

If the Limiting Condition for Operation is. restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to' place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in:

1.

At'least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

At least HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 3.-

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

. here corrective measures are completed that permit operation under the ACTION ~

W requirements, the ACTION may be taken.in accordance with the specified time limits as measuredLfrom the time of failure to meet the' Limiting Condition for Operation.

Exception: to.these requirements are stated in the individual Specifications.

ThisiSpecification is'not appiicable in OPERATIONAL CONDITIONS 4 or 5.

3.0.4 Entry into an OPERATIONAL CONDITION or other'specified condition shall not be made.when the conditions for the Limiting condition;for Operation'are not met.and the associated ACTION requires a shutdown 'if theyLare not met within<a specified time interval.

Entry into an OPThe 'IONAL-CONDITION or other~specified condition may be made in accordance With the ACTION requirements when conformance to them permits: continued operation of the facility for an unlimited period of time.

This provision shall not prevent passage through or to'0PERATIONAL CONDITIONS as required to comply with ACTION requirements.

. Exceptions to these requirements are stated in the individual Specifications.

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' RIVER BEND - UNIT 1 3/4 0-1 Amendment No. 47

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APPLICABILITY SURVEILLANCE REQUIREMENTS l

-40.1 Surveillance hequirements snall be met during the OPERATIONAL CONDITIONS or other conditi.ons specified for individual' Limiting Conditions for Operation-H unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified

'i surveillance interval with'a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement witM n allowed surveil-lance interval, defined by Specification 4.0.2, shall constitute non-compliance with the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identi-fied that a SURVEILLANCE REQUIREMENT has not been performed.

The ACTION, requirements may be delayed for'up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are-less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance requirements do not have to be performed l

on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition sha11Lnot be made unless the Surveillance Requirement (s) associated with the Limiting Condition for.0peration have been performed within the applicable surveillance interval or as otherwise specified.

This provision shall not prevent; passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing ot ASME Code Class 1, 2, & 3 components shall be applicable as follows:

a.

Inservice _ inspection of ASME Code Class 1, 2, and 3 components and 1

inservice: testing of ASME Code Class 1, 2,'and 3 pumps-and valves shallibe performed-in accordance with Section XI of the ASME Boiler 1

and-Pressure Vessel Code ~and applicable Addenda as. required by'10 CFR 50, Section 50.55a(g), except where specific written relief has-

~been granted by the Commission pursuant to 10 CFR.50, Section 50.55a(g)

(G) (1).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vesse1~ Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

RIVER BEND UNIT 1 3/4 0-2 Amendment No. AZ, 47

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.. REACTIVITY CONTROL SYSTEMS

'3/4;1.3 CONTROL RODS-

" CONTROL ROD OPERABILITY g

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' LIMITING CONDITION FOR OPERATION 3.1.3.1 :All control rods shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

' ACTION:

a.

Witn one control rod inoperable, due to being immovable as a result of excessive /riction er mechanical interference, or known to be untrippable:

1.

Within one hour:

W a)

Verify that the inoperable control rod, if withdrawn, is separated from all other_-inoperable control rods by_ at least two control' cells in all directions.

-b)

Disarm the-associated directional control valves

either:

1)

Electrically, or y

2)

Hydraulically by. closing the drive water and exhaust water isolation valvas.

Otherwise, be in at 'least. HOT SHUTDOWN within the ned 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

'2.

Restore _the inoperable control rod to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at'least H01 SHUTDOWN within'the next.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With one or'more control =-rods trippable but inoperable for causes other than addressed in~ ACTION a, above:

1.

If the inoperable control rod (s) is withdrawn, within one~ hour:

a)

Verify that the-inoperable withdrawn control rod (s) is separated from all other' inoperable withdrawn control rods by at least-two control cells in all directions,'and b)

Demonstrate the insertion capability of the inoperable e

1 withdrawn control rod (s) by inserting the control rod (s) at' least one notch'by drive water pressure within the normal operating range **.-

May be rearmed intermittently, under administrative control, to permit test-ing associated with restoring the control rod to OPERABLE status.

- The inoperable control rod may then be withdrawn to a position no further withdrawn than its position when found to be inoperable.

tRIVER BEND - UNIT 1 3/4 1-3 p

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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued)

Otherwise, insert the inoperable withdrawn control rod (s) and disarm the associated directional control valves

either:

a)

Electrically, or b)

Hydraulically by closing the drive water and exhaust water isol ion valves.

2.

If the inop..'able control rod (s) is inserted, with'n one hour disarm the associated directional control valves

either:

a)

Electrically, or b)

Hydraulically by closing the drive water and exhaust water isoiation valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I c.

With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , d.

With one scram discharge volume vent valve and/or one scram discharge volume drain valve inoperable and open, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , e.

With two scram discharge volume vent valves and/or two scram discharge volume drain valves inoperable and open, restore one valve in the vent line and one valve in the drain line to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and restore all valves to OPERABLE status within the next 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months or close at least one vent valve and one drain valve and be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

f.

With any scram discharge volume vent valve (s) and/or any scram discharge volume drain valve (s) inoperable and closed except when required by ACTION statement e. above, restore all valves to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

a.

At least once per 31 days verifying each valve to be open,** and

May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

- These valves may be closed intermittently for testing under administrative controls.

RIVER BEND - UNIT 1 3/41-4 Amendment No.

26, 47

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1c REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR-OPERATION (Continued)

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(

ACTION:

. Continued) 4

-4.

No " slow" control rod, " fast" control rod with individual scram insertion time in excess of the-limits of ACTION a~.2,'or other-wise inope~able control rod occupies an adjacent location in any direction, including the diagonal,;to another such control rod.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With a " slow" control rod (s) not satisfying ACTION a.1, above:

1.

Declare'the " slow" control rod (s) inoperable, and 2.

Perform the Surveillance Requirements of Specification 4.1.3.2.c 7

at least once per 60 days when operation is continued with three-

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or more " slow" control rods declared inoperable.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With the maximum scram insertion time of cae or more control rods exceeding-the maximum scram insertion time-limits of Specifica-tion 3.1.3.2 as determined by Specification 4.1.3.2.c, operation may continue provided that:

1.

" Slow" control rods, i.e., those which exceed the limits of.

. Specification 3.1.3.2, do not make up more than 20%'of.the 10%

sample offcontrol rods tested.

2.

Each of these " slow" control rods satisfies the limits of' 4

ACTION a.'1.

3.!

Th'e eight adjacent control rods surrounding each " slow" control.

rod are:

a).

Demonstrated through measurement within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to satisfy the maximum scram insertion time limits of Specifica-tion 3.1.3.2, and b)

OPERABLE.

4.

The' total number of " slow" control rods,:as determined.by Speci-fication 4.1.3.'2.c, when added to the sum of ACTION a.3, as -

determined by Specification 4.1.3.2.a and b, does not exceed 5.

<c Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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-i RIVER BEND - UNIT 1 3/4 1-7 Amendment No. 47 4

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-h REACTIVITY CONTROL SYSTEMS

~ SURVEILLANCE REQUIREMENTS 4.1.3.2-The maximum scram insertion time of the control rods shall be demonstrated'through measurement with reactor coolant = pressure greater than or equal to 950 psig and, during single control rod scram tism tests, the control rod drive pumps isolated from the accumulators:

a.

For all-control-rods prior to THERMAL POWER' exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS or after a reactor shutdown _that is greater than 120 days, s

b.

For specifically affected individual control rods *1 following maintenance on or modification to the-control rod or control rod.

drive system which could affect the scram insertion time of those.

specific control rods, and.

c.

For at least 10% of the control rods; on;2 tsStting basis, at least once per 120 days of POWER OPERATION._,

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The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 providad this surveillance is completed prior to entry'into OPERATIONAL CONDITION 1.

RIVER BEND - UNIT 1 3/4 1-8

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REACTIVITY CONTROL-SYSTEMS j

ICONTROL ROD SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION-3.1;3.3 All' control rod scram accumulators shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2-and 5*.

I ACTION:

a.-

In OPERATIONAL CONDITIONS 1 or 2:

1..

With one c.ontrol rod scram accumulator inoperable, within 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s:

a).. Restore the inoperable accumulator to OPERABLE status, or.

b)

Declare the control rod associated with the inoperable-accumulator inoperable.

Otherwise,: be in at least-HOT SHUTDOWN:within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2n With more than one control rod scram accumulator inoperable,'.

declare the associated control rods inoperable and:

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- a)'

If the control rod associated with any inoperable; scram accumulator-is' withdrawn, immediately verify.that at least i

one control' rod drive pump is operating by-inserting-at least one: withdrawn control rod at'least one notch or place

-the reactor mode switch in the Shutdown position.

b)

Insert-the inoperable control rods and disarm the associated-directional control valves either-5 1)'

Electrically, or 2)

Hydraulically by closing the drive. water and exhaust-water isolation valves.

,i Otherwise,- be in at least HOT. SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1 b.-

In OPERATIONAL CONDITION,5*:

1.

With one withdrawn control' rod with its associated scram accumu-

~1ator inoperable, insert the affected control rod and disarm the associated directional control valves within one hour, either:

J 4

5 "At least the. accumulator associated with each withdrawn control rod.

Not applicable to control' rods removed per Specification 3.9.10.1 or 3.9.10.2.

' RIVER BEND - UNIT 1 3/4 1-9

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, REACTIVITY CONTROL SYSTEMS-CONTROL ROD SCRAM ACCUMULATORS:

LIMITING CONDITION FOR OPERATION ACTION: -(Continued) y a)

Electrically, or j

b)'

Hydraulically by closing the drive water and exhaust water isolation valves.

2.

With more than one withdrawn control rod with the-associatedL scram accumulator inoperable and with no control rod. drive ~ pump a

operating, immediately place the reactor' mode switch in the-

.j' Shutdown position, j

3.

The provisions of Specification 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS I

4.1.3.3 Each control rod scram accumulator shall be determined'0PERABLE:

At least once per 7 days by verifying that theIindicated pressure is 1

a.

greater than'or equal to 1520 psig unless.the control-rod is inserted-and disarmed or scrammed.

b.

- At least once per 18 months by:

1 1.

Performance of a:

.i Y

a)

CHANNEL FUNCTIONAL' TEST of the leak l detectors, and-b)

CHANNELCALIBRATIONof'thepressuredetectors,andverifping an alarm setpoint of > 1520 psig on ~ decreasing ' pressure; 2.

Measuring and recording the time fortup to 10 minutes' that each i

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individual accumulator check' valve maintains the associated 4

1 accumulator pressure above the alarm set-point with no control;

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tod drive' pump ' operating.

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RIVER BEND - UNIT 1 3/4 1-10 Amendment No. 47

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" REACTIVITY CONTROL SYSTEMS CONTROL ROD'ORIVE COUPLINil LIMITING CONDITION FOR OPERATION

-l 3.1. 3. 4~ All. control rods shall be coupled to their drive mechanisms.

APPLICABILITY:' OPERATIONAL CONDITIONS 1, 2 and 5*..

ACTION:

a.

.In'0PERATIONAL CONDITION 1 and 2 with one control rod not coupled t'o its associated drive mechanism, within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

1.

If permitted by the RPCS,-insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:

a)

' Observing any indicated response of the nuclear instrumenta--

tion, and b)

-Demonstrating that the control rod will not go to the overtravel position.

.c)

The provisions of Specification 3.0.4 are not applicable.

.l,

.2.

If recoupling is not accomplished on the first attempt or, if not-permitted by the RPCS, then until permitted by.the RPCS, declare the control rod inoperable, insert.the control rod and disarm'the

. associated directional control valves ** either:

a).

Electrically, or b)

Hydraulically by closing the drive water'and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

+

b.

In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to its-associated drive mechanism, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , either:

0 1.

Insert the control rod to accomplish recoupling and verify S

recoupling by withdrawing the control rod'and demonstrating that 7

the control rod will not go to the overtravel position, or i

"At least each withdrawn control rod.

Not applicable to control rods removed h"

per Specification 3.9.10.1 or 3.9.10.2.

- May be rearmed' intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

A RIVER BEND - UNIT 1 3/4 1-11 Amendment No. 47

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'REACTIVIT CONTROL SYSTEMS ~

- CONTROL R00 DRIVE COUPLING LIMITING CONDITION FOR OPERATION ACTION:

(Continued) 2.

If recoupling is-not accomplished, insert the control rod and disarm the associated directional control valves

either:

i a)-

Electrically, or-j b)-

Hydraulically by closing the drive water and exhaust water d

isolation valves.

l l

J SURVEILLANCE REQUIREMENTS 4

4.1.3.4 Each affected control rod shall=be demonstrated to be coupled to its lI drive mechanism by cbberving any indicated-response of the nuclear instrumen-tation while withdrawing the control ~ rod to~the fully withdrawn position and 1;

Lthen verifying that the control rod drive does not.go to the overtravel position-a.

' Prior to_ reactor criticality after completing CORE AL1ERATIONS that 1 y could have affected-the control rod drive coupling integrity, b.

Anytime the control rod is withdrawn to the " Full out" position in j;

subsequent operation, and j

- l c.

Following maintenance on or modification to the control rod or-control rod drive system which could have affected the control rod-9 drive coupling integrity.

, i]

- i

- il

May-be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

a RIVER' BEND'- UNIT 1 3/4 1-12 Amendment No. 47

REACTIVITY CONTROL SYSTEMS n

CONTROL ROD POSITION INDICATION LIMITING CONDITION FOR OPERATION 3.1.3.5. The control rod position indication system sha).

OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 5*.

ACTION:

a.

In OPERATIONAL-CONDITION 1 or 2 with one or more control rod position p

~

indicators inoperable, within one hour:

1.

Determine the position of the control rod by an alternate control rod position indicator, or 2.

Move the control rod to a position with an OPERABLE position indicator, or

~3.

When THERMAL POWER is:

a)

-Within the low power setpoint of the RPCS:

1)

Declare the control rod inoperable, and-2)

Verify the position and bypassing of control' rods with inoperable " Full-in" and/or." Full-out" position indicators by a second licensed operator or other technically

' qualified members of the unit technical staff.

b)

Greater than the low power setpoint of the RPCS, declare the control rod inoperable, insert the control rod and' disarm the associated directional control valves ** either:

1)

-Electrically,-or 2)

Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within the next.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

. In OPERATIONAL CONDITION 5* with no position indicators of a-with-drawn control rod OPERABLE, move the control rod to a position with an OPERABLE position indicator or insert the control rod.

"At least each withdrawn control rod.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

- May-be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

RIVER BEND - UNIT 1 3/4 1-13 Amendment No. 47

.,-l

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w 18

,.s.

E ACTIVITY: CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS i

c 4.1.3'.5' The control. rod position' indication system shall be determined OPERABLE

.by - veri fyi ng:.

a.

At least once per 24' hours that the position'of each control rod is

-indicated and-b-

That the indicated control rod position changes during the movement of.the control rod drive when performing Surveillance Requirement' 4.1.3.1.2.

1

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1 1l l

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s yn RIVER BEND - UNIT l' 3/4 1-14 1

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i l3/4.3 INSTRUMENTATION 3/4.3;1 REACTOR PROTECTION SYSTEM INSTRUMENTATION

LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table'3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM

. RESPONSE TIME as shown in Table 3.3.1-2.

l APPLICABILITY:

As shown in Table 3.3.1-1.

y ACTION:

a.

With the number of OPERABLE channels less than required by the Mini-mum OPERABLE Channels per Trip System requirement for one trip system, place tiie inoperable channel (s) and/or that trip system in the tripped condition

within one hour.

b.-

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per. Trip System requirement for both trip systems,.

place at least one trip system ** in the tripped condition within one hour'and take.the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the-frequencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.***

-4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each react'or trip functional. unit shown in Table 3.3.1-2 shall be demonstrated to be within its-limit at least once per 18 months.-

Each test shall' include at least one channel per trip system such that all channels:are tested at least once every N times 18 months where N is the total number of redundant-channels in a specific reactor trip system.

'*An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In-these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.-3.1-1 for that Trip Function shallbe taken.

- The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur.

When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable' channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition. 'The requirement to place a trip system in the tripped condition does not apply to Functional Units 6 and 10 of Table 3.3.1-1.

- - Logic System Functional Test period may be extended as identified by note 'p' on Table 4.3.1.1-1.

-RIVER BEND - UNIT 1 3/4 3-1 Amendment No.8, 47 l

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iTABLE 1 3 1-1L

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REACTOR PROTECTION SYSTEM INSTRUMENTATION-

~

J APPLICABLE MINIMUM-

.g

, OPERATIONAL OPERABLE CHANNELS..

FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)'

ACTION-C izi 1.

I'ntermediate Range Monitors:

H a.

Neutron Flux - High 2:

13 1

3(b)4 3

2.

H 5

3' 3'

b.

Inoperative-2 3

1 3, 4 3

2 5

3 3

2.

Average Power Range Monitor (C):

l a.

Neutron Flux - High, Setdown 2

3 1

~ (b)4 3

2 3

l-s*

g 5

3 3~

r w

{~

E b.

Flow Biased Simulated Thermal-I Power - High-1 3

4 c.

Neutron Flux - High 1

3

.4' d.

Inoperative

'1, 23 3

1

3,.4 3

2 5-3 3

3.

Reactor Vessel Steam Dome (d)

I Pressure - High 1, 2 2

-1 4.

Reactor Vessel Water Level - Low,.

2 1.

l Level 3 1,-2 5.

Reactor Vessel Water Level-High, Level 8

.1,)-

2-A i

6.

Main Steam Line.Isoletion-Valve --

Closure

~

1(*):-

4~

10 7.

Main Steam Line Radiation -

I High L1,f2(d)

~ 2' 5

8.

Drywell-Pressure.

High:

'1, 2(f);

2

.1

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~ '

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-TABLE 4'.3.1.1-1 (Continued).

A

-REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS'.

~

2-

. co

~

(f)' The LPRMs?shall 'be calibrated at-least once-per~1000 effective-full: power hoursi(EFPH) using the-TIP system. c.

g (g) Calibrate Rosemount trip unit setpoint at' least once per. 31 days.-

y (h) Verify measured. drive flow to be less than or equal-to established drive flow at the existing flowT control ~ valve' position.

l (i) This calibration ~shall: consist of verifying-the simulated thermal power time constant is within the.

g l

limits specified in the COLR.

(j) This function-is not required to.be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.'1.

(k) With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 1j 3.9.10.2.

-(l) This-function is not? required to be 0PERABLE when DRYWELL INTEGRITV is not required per Specifica-tion 3.10.1 l

y (m) Verify the Turbine Bypass Valves are closed when THERMAL POWER is greater than or equal to 40% RATED o

=

THERMAL POWER.

l y

(n) The CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION shall include the turbine first stage pressure.

instruments.

e (o) The CHANNEL CALIBRATION shall exclude the flow reference transmitters; these transmitters shall be calibrated at least once per 18 months.

(p) This~ period may be extended to the first refueling outage, not to exceed 9-15-87.

l i

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pjt

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o.

.ICTRUMENTATION:

3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION 6

f q

. LIMITING CONDITION'FOR OPERATION

= 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 S

shall be OPERABLE with their trip setpoints set consistent with the values shown

.in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE W

TIME as shown in Table 3.3.2-3..

APPLICABILITY:

As shown in Table 3.3.2-1.

" ACTION:

. ith an isolation actuation instrumentation channel trip-setpoint W

a.

'less conservative than-the value shown in the Allowable Values column of Table 3.3.2-2,- declare the channel inoperable until the channel is restored to'0PERABLE ' status with its trip setpoint adjusted consistent with-the Trip Setpoint value.

l b.

With the number of 0PERABLE channels less than required by.the Minimum OPERABLE Channels per Trip System requirement for one' trip system, place the inoperable channel (s) and/or that trip system in the tripped-O condition

within one hour..

c.

-With the number of OPERABLE channels less than required by the Minimum

-OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in-the tripped condition within one' hour and.take thetACTION required by Table.3.3.2-1.

n,

AnLinoperable channel need not be placed in the tripped condition.where-this.

would cause-the Trip Function to occur.. In these cases, the inoperable channel

.shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be'taken.

'**The, trip system need not be placed in.the tripped condition if this would cause

'theTTrip Function to occur.

When a trip system can.be placed in the tripped l condition without-causing the Trip Function to occur, place'the trip system with the:most inoperable: channels in the tripped condition; if both systems have the same number of~ inoperable channels,: place either trip system in'the tripped conaition.

4

. RIVER BEND - UNIT 1 3/4 3-10 Amendment No. 47 s

7

p i

?

TABLE 3;3.6-l'(Continued)'

CONTROLiR00 BLOCK INSTRUMENTATION ACTION

< ACTION 60:

Declare the RPCS inoperable and take the ACTION required by Specification 3.1.4.2.

ACTION 61 With'the number of OPERABLE Channels:.

a.

One less than required by the Minimum OPERABLE ChannelsL per Trip Function requirement,. restore the inoperable channel to OPERABLE status within-7 days or place;the' inoperable-channel-in the tripped condition.within-the next hour.;

-b b.

Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirem9nt, place at least one inoperable channel in the tripped condition within

. I; one hour.

With the' number of OPERABLE channels less than required by the-

' ACTION 62 Mi.nimum OPERABLE Channels per T"ip. Function requirement, place-the inoperable channel in.the tripped condition within.one hour...

[~

s NOTES

. ith more than one control rod withdrawn.

Not applicable,to: control rods W

dremoved'per Specification 3.9.10.1"or 3.9.10;2.

m

-0PERABLE channels must be. associated with SRM. required OPERABLE per 9

Specification 3.9.2.

{' ~

L(a)J This. function shall:be automatically bypassed if detecter count rate is

> 100. cps or theEIRM. channels are on range'3 or higher.

'(b).Thisofunction shall_ be automatically bypassed when_ the associated IRM,

. channels are'_on range.8 or higher.

(c) -This-funct' ion shall be automatically bypassed when the IRM channels arc.

on range 3 or higher.

.(d) This function shall be automatically bypassed when the IRM' channels are on range-1.

1 1

. RIVER' BEND UNIT 1 3/4 3-61 Amendment No. 47 h

TABLE 3.3.6-2.:

CONTROL BLOCK INSTRUMENTATION SETPOINTS'

~

x TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE

_. q 1m

- 1.

R00 PATTERN CONTROL SYSTEM-a.

Low Power-Setpoint

-27.5 i 3% of RATED THERMAL POWER 27.5 i-7.5% of RATED THERMAL

("

POWER m

E b.

High Power Setpoint 5 67.9% of RATED THERMAL POWER 1 68.2% of RATED THERMAL POWER

[

-2.

APRM z

a.

Flow-Biased Neutron Flux Upscale-

[

1) Two Recirculation Loop

.5 0.66W + 45%*.

Operation 5 0.66W + 42%*

c 2). Single; Recirculation Loop Operation

< 0.66W + 36.7%*

< 0.66W + 39.7%*

b.

Inoperative NA NA d.

Neutron Flux Upscale

->5% of RATED THERMAL POWER 2 3% of RATED THERMAL POWER-c.

Downscale Startup 512% of RATED THERE AL POWER

$ 14% of RATED THERMAL POWER E

3.

SOURCE RANGE MONITORS-a.

Detector not full in-NA NA 5

5 b.

Upscale.

< 1 x 10 cps

< 1.6 x 10 cp,

{

ro c.

Inoperative HA NA d.

Downscale 1 0.7 cps 1 0.5 cps **

4.

INTERMEDIATE RANGE MONITORS a.

Detector not full in NA NA b.

Upscale

$ 108/125 division-of full

$ 110/125 division of full scale scale c.

Inoperative NA NA d.

Downscale 1 5/125 division of full 2 3/125 division of full g

scale scale m

5.

SCRAM DISCHARGE VOLUME a.

Water Level-High - LISN602A

< 18.00"

< 21.12" LISN6028 7 18.00" 7 21.60" 2

P 6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.

Upscale 5 108% of rated flow

$ 111% of rated flow-d

The Average Power Range Monitor rod block function is varied as a function of' recirculation loop flow (W).

The trip setting of this function must be maintlined in accordance with Specification 3.2.2.

- Provided signal-to noise ratio is 1-2, otherwise setpoint of 3. cps and allowable 1.8 cps.

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' INSTRUMENTATION 9

3/4.3.7 MONITORING INSTRUMENTATION ~

L

' RADIATION MONITO' RING' INSTRUMENTATION L,IMITING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels:shown in Table'

!3.3.7.1-1 shall be OPERABLE with their alarm / trip setpoints within the i

h specified. limits.

- APPLICABILITY:

As shown in Table 3.3.7.1-1.

ACTION:

a.

With a radiation monitoring int.trementation channel alarm / trip

-setpoint exceeding the value shown in Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the~--

ACTION-required,by Table 3.3.7.1-1.

mL c.

The provisions of Specification 3.0.3 are not applicable.

a:

SURVEILLANCE REQUIREMENTS-4.3.7.-1 : Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performances.of the CHANNEL-CHECK,-CHANNEL FUNCTIONALETEST and CHANNEL CALIBRATION operations-for the conditions and at the frequencies shown in Table 4.3.7.1-1.'

1 I.

' RIVER BEND - UNIT 1 3/4 3-65 Amendment No. 47 n:. ':

4

.~

. TA8LE 3.3.7.1-1

- y~

RADIATION MONITORING INSTRlMENTATION E

MINIMUM' CHANNELS-APPLICABLE ALARM / TRIP e

INSTRUMEieTATION OPERABLE COSITIONS SETPOINT _

ACTION i'i 1.

Main Control Room Ventilation Radiation Monitor a.

Local Intake 2

1,2,3,5 and *

< 0.97 x 10 5 pCi/cc 70 I

b.

Remote Intake 1'

1,2,3,5 and *

$ 0.97 x 10 s pCf/cc ")

71, 2.

Area Monitor a.

Fuel Building g

Storage Pool

-< 15 mR/hr(a) 77 Spent Fuel 1

s w

3.

Main Condenser Offgas E

Post-Treatment System Effluent Monitoring System a.

Noble Gas Activity Monitor - (Providing Alarm and Automatic Termination of t

Release) 1

$ 5.08 x 105 cpm 72 4.

Condenser Air Ejector Pretreatment Radioactivity Monitor (Prior to Input to i.

Holdup System) l a.

Neble Gas Activity g)

Monitor 1

$ 2.48 x 10* mR/hr 73 l

l 4

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m-y a-,-

,w

,gs, m.-

a*.m

-e

,,,-.-,,4.

_e,-m

+

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,. mn e

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.-~

w

y ; ~w-

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J TABLE 3.3.7.1-1 (Continu ;)

2 RADIATION MONITORING INSTRUMENTATION g.

Eg TABLE NOTATIO",

.. E -

4

When irradiated fuel is being handled in the primary containment or the Fuel Building.

g

- During operation of the main condenser air ejector.

(a) Alarm only.

With fuel in the spent fuel storage pool.

Y.

Y O

t

'atte_

i TABLE 3.3.7.1-1 (Continued)

RADIATION MONITORING INSTRUMENTATION ACTION ACTION 70 a.

With one of the required monitors inoperable, restore the in-1 operable channel to OPERABLE status within 7 days *, or, withir l

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of the control room sia conditioning system in the emergency mode of operation.

b.

With both of the required monitors inoperable, initiate and maintain operation of the control room air conditioning system in the emergency mode of operation within one hour.

ACTION 71 -

With the required monitor inoperable, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 72 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab sam-ples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .*

}

ACiION 73 -

With the number of channels OPERABLE less then required by the Minimum Channels OPERABLE requirement, releases may continue to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

provided:

.l a.

The offgas system is not bypassed, and b.

At least one post treatment noble gas activity effluent monitor is OPERABLE;

~

f Otherwise, be in at least STARTUP within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , m

"The provisions of Specification 3.0.4 are not applicable.

a RIVER BEND - UNIT 1 3/4 3-68 Amendment No. 47 E

~,

~

TABLE 4.3.7.1-1 MONITORING INSTRUMENTATION SURVEILLANCE REQUIREENTS E

z CHANNEL CONDITIONS IN o

CHANNEL FUNCTIONAL CHANNEL idHICH SURVEILLANCE g

INSTRUMENTATION CHECK TEST CALIBRATION REQUIRED Z

1.

Rain Control Room g

Ventilation Radiation Monitor a.

Local Intake S

M R

1, 2, 3, 5 and

b.

Remote Intake 5

M R

1, 2, 3, 5 and

2.

Area Monitor a.

Fuel Building-

,g Spent Fuel Storage Pool S

M R

h 3.

Main Condenser Offgas Post-Treatment System Effluent Monitoring System a.

Noble Gas Activity Monitor -

(Providing Alarm and Auto-ratic Termination of Release) D Q

R 4.

Condenser Air Ejector Pretreatment Radioactivity Monitor a.

Noble Gas Activity Monitor D

Q R

When irradiatad fuel is-being handled in the primary containment or the Fuel Building.

- During operation of the main condenser air ejector.

With fuel in the spent' fuel storage pool.

__.______h-I

L i

1 INSTRUMENTATION SEISMIC MONITORING _ INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.

j APPLICABILITY:

At all times.

ACTION:

)

a.

With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, prepare and submit within the next 10 days a Special-Report to the Commission, pursuant to Specifica-r tion 6.9.2,. outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNC-TIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in-Table 4.3.7.2-1.

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 5 days following the seismic event.

Data shall be retrieved from actuated. instruments and analyzed to determine the magnitude of the vibratory ground motion.

Within 10 days, a Special Report shall be prepared and submitted to the Commission,

' pursuant to Specification 6.9.2, describing the magnitude, frequency spectrum and resultant effect upon unit features important to safety.

p RIVER BEND - UNIT 1 3/4 3-70 Amendment No. 47 w

INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

a.

With one or more meteorological monitoring instrumentation channels inoperable for more than 7 days, prepare and submit within the next 10 days a Special Report to the Commission, pursuant to Specifica-tion 6.9.2, outlining the cause of the malfunction and the plans for restor:ng the instrumentation to OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.3 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.

l i

l p

1 RIVER BEND - UNIT 1 3/4 3-73 Amendment No. 47 1

L i

l TABLEQ.'J.7.3-1 i

METEOROLOGICAL MONITORING INSTRUMENTATION f

MINIMUM INSTRUMENTS INSTRUMENT OPERABLE a.

Wind Speed 1

r 1.

Elev. 30 ft.

1 2.

Elev. 150 ft.

1 h

_ b.

Wind Direction 1.

Elev. 30 ft, 1

2.

Elev. 150 ft.

1 c.

Air Temperature Difference 1.

Elev. 30/150 ft.

1 e

- t 9

k RIVER BEND - UNIT 1 3/4 3-74 e

i

w INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPER,ATION 3.3.7.8 As a minimum, the fire detection instrumentation for each fire detection 4

zone shown in Table 3.3.7.8-1 shall be OPERABLE.

APPLICABILITY:

Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

a.

With any, but no more than one-half the total in any fire zone, Func-tion A fire detection instruments shown in Table 3.3.7.8-1 inoperable, restore the inoperable Function A instrument (s) to OPERABLE status within 14 days or, within the next hour, establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour.

If the instrument (s) is located inside the contain-ment, inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.8 and 4.6.2.6.

b.

Vith more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3.7.8-1 inoperable, or with any Function B fire detection instruments shown in Table 3.3.7.8-1 inoperable, or with any two or more adjacent instruments shown in Table 3.3.7.8-1 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour.

If the instrument (s) is located inside the con-tainment, inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.8 and 4.6.2.6.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.8.1 Each of the above required fire detection instruments which are accessible during unit operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fire detectors which are not accessible during unit operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.7.8.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instru-ments shall be demonstrated OPERABLE at least once per 6 months.

RIVER BEND - UNIT 1 3/4 3-87 Amendment No. 47 z

f l

TABLE 3.3.7.8-1 FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION TOTAL INSTRUMENTS OPERABLE

HEAT FLAME SMOKE (x/y)

(x/y)

]

I I.

CONTROL BUILDING q

ZONE SD-1 HVAC ROOM, EL 115'0" & 116'0" 6/0 SD-2 HPCS SWGR, EL 115'0" & 116'0" 3/0 SD-3 BATTERY ROOMS (3) & DC EQUIP RMS, EL 115'0" & 116'0" 8/0 SD-4 HVAC ROOM, EL 98'0" 6/0 50-5 STBY SWGR ROOM B, EL 98'0" 3/0 SD-6 STBY SWGR ROOM A, EL 98'0" 3/0 SD-15 HVAC ROOM 1A, EL 70'0" 2/0 SD-16 HVAC ROOM 18. EL 70'0" 2/0 SD-17 CABLE VAULT, EL 70'0" 0/3 S0-18 CABLE VAULT, EL 70'0" 0/4 SD-19 CABLE VAULT, EL 70'0" 0/9 S0-20 CABLE CHASES, EL 70'0" 17/0

)

50-50 CABLE CHASES, EL 98'0" 9/0 SD-54 CABLE CHASES, EL 116'0" 10/0 SD-60 125 VDC SWGR & BATT CHGR, EL 115'0" & 116'0" 10/0 50-61 GENERAL AREA, EL 98'0" 8/0 50-125 PGCC PANEL MODULE, EL 136'0" 0/8 10/0-50-126 PGCC PANEL MODULE, EL 136'0" 0/8 13/0 SD-127 PGCC PANEL MODULE, EL 136'0" 0/8 11/0 SD-128 PGCC PANEL MODULE, EL 136'0" 0/8 9/0 50-129 PGCC PANEL MODULE, EL 136'0" 0/9 12/0 S0-130 PGCC PANEL MODULE, EL 136'0" 0/8 11/0 50-131 PGCC PANEL MODULE, EL 136'0" 0/9 17/0 SD-132 PGCC PANEL MODULE, EL 136'0" 0/8 17/0 J

50-133 PGCC PANEL MODULE, EL 136'0" 0/8 13/0 SD-134 PGCC PANEL MODULE, EL 136'0" 0/8 12/0 50-135 PGCC PANEL MODULE, EL 136'0" 0/8 9/0' l

50-136 PGCC PANEL MODULE EL 136'0" 0/9 9/0 SD-137 PGCC PANEL MODULE, EL 136'0" 0/8 8/0 138 PGCC PANEL MODULE, EL 136'0" 0/8 10/0 S0-139 PGCC PANEL MODULE, EL 136'0" 0/12 12/0 i

50-140 PGCC PANEL MODULE, EL 106'0" 0/8 14/0 S0-141 PGCC PANEL MODULE, EL 136'0" 0/8 13/0

/

SD-142 PGCC PANEL MODULE, EL 136'0" 0/9 16/0 (x/y):

x is number of Function A (early warning fire detection and notifi-cation only) 4...truments.

y is nue:,r of Function B (actuation of fire suppression systems and early warning fire detection).

j RIVER BEND - UNIT 1 3/4 3-88

+ 'L 1

i INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.9 The locae part detection system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a.

With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit within the next 10 days a Special Report to the Commission, pursuant to Specification 6.9.2, outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable, o

d SURVEILLANCE REQUIREMENTS 4.3.7.9 Each channel of the loose part detection system shall be demonstrated' OPERABLE by performance of a:

r a.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.

CHANNEL CALIBRATION at ' *ast once per 18 months.

l I

l 1.

l L

l l

t RIVER BEND - UNIT 1 3/4 3-93 Amendment No. 47

INSTRUMENTATION

' RADIOACTIVE LIQUID EFFLUENT '40NITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY:

At all times.

ACTION:

I a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

b.

With less than the minimum number of radioactive liquid effluent 4

monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1.

Restore the inoperable instrumentation to OPERABLE status within the time specified in ACTION or explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

The provisions of Specification 3.0.4 are not applicable.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.

i

)

RIVER BEND - UNIT 1 3/4 3-94 Amendment No. 47

i INSTRUMENTATION l

i RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip

setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY:

As shown in Table 3.3.7.11-1.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip

setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or exp',ain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

The provisions of Specification 3.0.4 are not applicable.

c.

The provisions of Specification 3.0.3 are not applicable.

SUREVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel.

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.11-1.

The alcrm/ trip setpoints for the Explosive Gas Mixture in the Main Condenser:

Offgas Treatment System are set in accordance with Specification 3.11.2.6.

1 I

L

-RIVER BEND - UNIT 1 3/4 3-99 Amendment No. 47 L

TA8LE 3.3.7.11-1

x, E-

.1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORIPG INSTRUMENTATION

5 MINIMUM CHANNELS E

-INSTRUMENT OPERABLE APPLICABILITY ACTION Z

1.

Maire Condenser Offgas Treatment System g

Explosive Gas Monitoring System (for systems designed to withstand the effects of a hydrogen explosion) a.

Hydrogen Analyzers (downstream 123 of the recombiner) 1 2.

Main Plant Exhaust Duct Monitoring w)

System a.

Noble Gas Activity Monitor 1

12?

8 b.

Iodine Sampler 1

124 c.

Particulate Sampler 1

124' d.

Effluent System Flow Rate Monitor 1

121 e.

Sampler Flow Rate Monitor-1 121 9'

.-e.,.v.

w, y,---

...,--,w.-.

m m-r-

-,4--

v..

m.

I i

TABLE 3.3.9-1 (Conti.1ued)-

l l

i ACTION 150 -

a.

With one channel inoperable, place the inoperable channel in the tripped condition # within one hour or declare the

-l associated system inoperable.

b.

With more than one channel inoperable, declare the associated l

system inoperable.

l ACTION 151 -

,a.

With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or be i

in~at least HOT SHUTDOWN within 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i b.

With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 152 -

Declare the associated Containment Ventilation System inoperable.

ACTION 153 -

a.-

With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the

~r inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i b.

With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one of the inoperable channels to OPERABLE status l

within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i

Provid9d this does not actuate the system.

o l

l RIVER BEND - UNIT 1 3/4 3-109 Amendment No. 47 x

- cw = g.. - - '

-= : -

-e 7 _..j TABLE 3.3.9-2 E-g

- PLANT--SYSTEMS ACTUATION INSTRUMENTATION SETPOINTS

.E' ALLOWA8LE

-E TRIP FUNCTION TRIP SETPOINT VALUE g-1.

PRIMARY CONTAINMENT VENTILATION SYSTEM -

q UNIT COOLER A AND B a.

Drywell Pressure-High

$ 1.68 psig

$ 1.88 psig b.

Containment-to-Ant /lus AP-High

-21.98 1 0.22" H O

-11. 98 + 0. 27, - 0. 31" H O 2

2 c.

Reactor Vessel Water Level-Low Low d.

Timer

~>-143 inches *

->-147 inches Low Level 1 600 i 35 seconds 600 1 45 seconds 2.

FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM Reactor Vessel Water Level-High Level 8 5 51 inches *-

$ 52.5 inches a.

Y C

o

See Bases Figure 8 3/4 3-1.

b 4

9

REACTOR COOLANT SYSTEM REACTOR STEAM DOME LIMITING CONDITION FOR OPERATION 3.4.6.2 The pressure in the reactor steam dome shall be less than 1045 psig.

APPLICABILITY:

OPERATIONAL CONDITIONS 1* and 2*.

ACTION:

With the reactor steam dome pressure exceeding 1045 psig, reduce the pressure to less than 1045 psig within 15 minutes or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i SURVEILLANCE REQUIREMENTS 4.4.6.2 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , the reactor steam dome pressure shall be verified to be less than 1045 psig.

a f

1 "Not applicable during anticipated transients.

l RIVER BEND'- UNIT 1 3/4 4-25 l.-

REACTOR COOLANT SYSTEM 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.4.7 Two main steam line isolation valves (MSIVs) per main steam line shall be OPERABLE with closing times greater than or eaual to 3 seconds and less than or equal to 5 seconds.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With one or more MSIVs inoperable, maintain at least one MSIV OPERABLE in each-affected main steam line that is open and, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , either:

a.

Restore the inoperable valve (s) to OPERABLE status, or b.

Isolate the affected main steam line by use of a deactivated MSIV in the closed position.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.7 At least once per 18 months, each of the above' required MSIVs shall be demonstrated OPERABLE by verifying full closure between 3 and 5 seconds when tested pursuant to Specification 4.0.5.

1 I

RIVER BEND - UNIT 1-3/4 4-26 AMENDMENT NO. 47 i

I l

REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.8 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.8.

~

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4 and 5.

ACTION:

a.

With the structural integrity of any ASME Code Class 1 component not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.

b.

With the structural integrity of any ASME Code Class 2 component not conforming to the above requirements, rotore the structural integrity of the affected component to within its limit or isolate the affected component prior to increasing the Reactor Coolant System.?.emperature above 200'F.

c.

With the structural integrity of any ASME Code Clast 3 component not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.

SURVEILLANCE REQUIREMENTS 4.4.0 No requirements other than Specification 4.0.5.

L P.IVER BEND - UNIT 1 3/4 4-27 AMENDMENT NO. 47 l

1

l I

~

REACTOR LOOLANT SYSTEM l

3/4.4.9 RES130AL HEAT REMOVAL HOT SHUTOOWN j

LIMITING CONDITION FOR OPERATION 3.4.9.1 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *,##

with each loop consisting of at'least:

a.

One OPERABLE RHR pump, and b.

Two OPERABLE RHR heat exchangers.

APPLICABILITY: OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR Cut-in permissive setpoint.

ACTION:

a.

With less than the above required RHR shutdown cooling mode loops OPERABLE, immediately initiate corrective action to return the re-quired loops to OPERABLE status as.soon as possible.

Within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability i

of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.

Be in at least COLD SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .**

J b.

With no RHR shutdown cooling mode loop or recirculation pump in opera-tion, immediately initiate corrective action to return at least one RHR shutdown cooling loop or recirculation pump to operation as soon as possible. Within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant tempersture and pressure at least once per hour.

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.9.1 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , at least one shutdown cooling mode loop of the residual heat removal system, one recirculation pump or alternate method shall be determined to be in operation and circulating reactor coolant.

0ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other loop is OPERABLE and in operation or at least one recirculation pump is in operation.

The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERABLE.

1. The.RHR shutdown cooling mode loop may be removed from operation during hydrostatic testing.

- Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUTOOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.

. RIVER BEND - UNIT 1 3/4 4-28

REACTOR COOLANT SYSTEM COLD SHUT 00WN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *,##

with each loop consisting of at least:

a.

One OPERABLE RHR pump, and b.

Two OPERABLE RHR heat exchangers.

APPLICABILITY:

OPERATIONAL CONDITION 4.

ACTION:

a.

With less than the above required RHR shutdown cooling mode loops OPERABLE, within une hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.

b..

With no RHR shutdown cooling mode loop or recirculation pump in opera-tion, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.

SURVEILLANCE REQUIREMENTS 4.4.9.2 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , at least one shutdown cooling mode loop of the residual heat removal system, one recirculation pump or alternate method shall be determined to be in operation and circulating reactor coolant.

0ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other loop is OPERABLE and in operation or at least one recirculation pump is in operation.

The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERABLE.

1. The shutdown cooling mode loop may be removed from operation during hydrostatic testing.

RIVER BEND - UNIT 1 3/4 4-29 Amendment No. 35,47

jh !

-EMERGENCY CORE COOLING SYSTEMS f

ACTION (Continued) c.

With one SPPS subsystem inoperable, restore the SPPS subsystem to OPERABLE status within 31 days or demonstrate the OPERABILITY of the remaining SPPS subsystem at least once per 31 days by:

1.

A functional test of the crescent area sump pump, and 2.

Demonstrating that the associated flow path can be aligned to the suppression pool.

d.

E th both SPPS subsystems inoperable, restore one SPPS subsystem to OPERABLE status within 7 days or:

1.

In OPERATIONAL CONDITION 1, 2, or 3 be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOWN within the following

+

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

f 2.

In OPERATIONAL CONDITION 4 or 5* provide at least one alternate pumpback method and demonstrate _the OPERABILITY of an alternate method within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, otherwise suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel e.nd lock the reactor mode switch in the shutdown position.

Establish PRIMARY CONTAINMENT INTEGRITY - FUEL HANDLING within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

l SURVEILLANCE REQUIREMENTS i

4.5.3.1 The suppression pool shall be determined OPERABLE by verifying the water level to be greater than or equal to, as applicable:

a.

19'6", at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , in OPERATIONAL CONDITION 1, 2 and 3.

i b.

13'3", at.least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , in OPERATIONAL CONDITION 4 and 5.

4.5.3.2 With the suppression pool level less than the above limit or drained in OPERATIONAL CONDITION 4 or 5*, at least once per 12-hours:

[

a.

Verify the required conditions of Specification 3.5.3.b to be satisfied, or L

b.

Verify footnote conditions

to be satisfied.-

4.5.3.3 At least once per 92 days, the SPPS shall be demonstrated OPERABLE'by:

1 a.

Verifying each crescent area sump pump develops 50gpm, and b.

Verifying the flow nath can be aligned to th.e suppression pool.

The suppression pool is not required to be OPERABLE in OPERATIONAL CONDITION 5 provided that the reactor vessel head is removed, the cavity is flooded, the upper containment fuel pool gate is open, and the water level is maintained within the limits of Specifications 3.9.8 and 3.9.9.

l RIVER BEND - UNIT 1 3/4 5-9 Amendment No.

J'9',

47 -

l 1

TABLE 3.6.1.3-1

=

ANNULUS BYPASS LEAKAGE PATHS i

1.

LEAKAGE PATHS TO THE FUEL BUILDING (6750 cc/hr limit)

PENETRATION Containment air lock IJRB*DRA2 2.

LEAKAGE PATHS TO THE AUXILIARY BUILDING (6750 cc/hr limit)

VALVE NO.

PENETRATION (DIV. I)

(DIV. II) 1KJB*Z31 1HVR*A0V165 1HVR*A0V123 1KJB*605E ICMS*SOV31A ICMS*SOV35C l

1KJB*605F ICMS*SOV31C ICMS*SOV35A 1KJB*601B ISSR*SOV131 ISSR*S0V130 1

Containment air lock IJRB*DRA1 CR0 removal hatch i

i 1

RIVER BEND - UNIT 1 3/4 6-7

i CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS

~

LIMITING CONDITION FOR OPERATION 3.6.1.4 Each primary containment air lock shall be OPERABLE with:

a.

Both doors closed, except at least one air lock door shall be closed When the air lock is being used for normal transit entry and exit f

through the containment, and b.

An overall air lock leakage rate in compliance with the limits of Specification 3.6.1.3.d when pressurized to Pa, 7.6 psig, and L

c.

The inflatable seal system air flask pressure > 90 psig.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2*, 3, and #.

ACTION:

9 a.

With one primary containment air lock door in one or both air locks inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed except as provided in a.3.

2.

With an air lock door in only one air lock inoperable, operation may then continue until performance of the next required overall l

air lock leakage test ** provided that the OPERABLE air lock door I

l is verified to be locked closed at least once per 31 days.

J 3.

With one air lock door in each air lock inoperable, operation may then continue with entry and exit permitted for up to 7

]

days ** provided that an OPERABLE air lock deur is verified to be locked closed after each entry or exit and c.n individual is dedicated to assure that two doors in an air lock are not opened simultaneously.

4.

Otherwise, in OPERATIONAL CONDITIONS 1, 2, or 3 be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

Otherwise, in Operational Condition #, suspend all operations involving handling of irradiated fuel in the containment, CORE ALTERATIONS, and operations with a potential for draining the reactor vessel.

"See Special Test Exception 3.10.1.

- The provisions of Specification 3.0.4 are not applicable.

l

When irradiated fuel is being handled in the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

RIVER BEND - UNIT 1 3/4 6-8 Amendment No. 47

e i

5 CONTAINMENT SYSTEMS 4

LIMITING CONDITION FOR OPERATION (Continued) 1 b.

With the interlock mechanism inoperable:

i 1.

Maintain at least one OPERABLE air lock door closed and either return the interlock to service within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock one i

OPERABLE air lock door closed.

1 2.

Personnel entry and exit through the air lock is permitted pro-vided one OPERABLE air lock door remains locked at all times and an individual is dedicated to assure that two doors are not open simultaneously.

c.

With a primary containment air lock inoperable, except as a result of an inoperable air lock door or an inoporable interlock mechanism, maintain at.least one air lock door closed; restore the inoperable l

air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or:

1.

In OPERATIONAL CONDITIONS 1, 2, or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 1

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

1 2.

In Operational Condition #, suspend all operations involving handling of irradiated fuel in the containment, CORE ALTERATIONS, and operations with.a potential for draining the reactor vessel.

d.

With one primary containment air lock door inflatable seal system air flash pressure instrumentation channel inoperable, restore the inoperable channel to OPERABLE status within 7 days or verify, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , air flask pressure to be > 90 psig.-

I SURVEILLANCE REQUIREMENTS 4.6;1.4 Each primary containment air lock shall be demonstrated OPERABLE:

a.

Within-72 hours ** following each closing, except at least once per l

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ** when the air lock is being used for multiple entries, by

. verifying seal leakage rate is in compliance with the limits in Specification 3.6.1.3.d when the gap between the door' seals is pressurized to Pa,.7.6 psig.

t L

-b.

By conducting an overall air lock leakage test at Pa, 7.6 psig, and verifying that the overall air lock leakage rate is within its limit:

1.

At least once per 6 months,**

When irradiated fuel is being handled in the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

- The provisions of Specification 4.0.2 are not applicable.

RIVER BEND - UNIT 1 3/4 6-9 Amendment No. 47 9y+

l 1

CONTAINMENT SYSTEMS.

SURVEILLANCE REQUIREMENTS (Continued) 2.

Prior to establishing PRIMARY CONTAINMENT INTEGRITY - OPERATING when the air lock has been used or when maintenance has been performed on the air lock that could affect the air _ lock sealing capability.

c.

At least once per 6 months by verifying that only one door in each j

air lock can be opened at a time.

i i

d.

By verifying the door inflatable seal system OPERABLE by:

1.

At least once per 7 days, verifying seal air flask pressure to be greater than or equal to 90 psig.

2.

At least once per 18 months, conducting a seal pneumatic system leak test and verifying that system pressure does not decay more than 1.28 psig from 90 psig within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

h i

i RIVER BEND - UNIT 1 3/4 6-9a Amendment No. 47 4

-~

CONTAINMENT SYSTEMS DRYWELL BYPASS LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.2.2 Drywell bypass leakage shall be less than or equal to 10% of the acceptableA//Edesignvalueof1.0ft2, APPLICABILITY:

When DRYWELL INTEGRITY is required per Specification 3.6.2.1.

ACTION:

With the drywell bypass leakage greater than 10% of the acceptable A//k design value of 1.0 fts, restore the drywell bypass leakage to within the limit prior to increasing reactor coolant system temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.2.2 At least once per 18 months *, the drywell bypass leakage rate test shall be conducted at an initial differential pressure of 3.0 psid and the A/Jk_

shall be calculated from the measured leakage.

One drywell airlock door shall remain open during the drywell leakage test such that each drywell door is leak tested during at least every other leakage rate test.

a.

If any drywell bypass leakage test fails to meet the specified limit, the schedule for subsequent tests shall be reviewed and approved by the Commission.

If two consecutive tests fail to meet the limit, a test shall be performed at least every 9 months until two consecutive tests meet t.he limit, at which time the 18 month test schedule may be resumed.

For.the first cycle only, this may be extended to coincide with the refueling outage, scheduled to begin September 15, 1987.

1 RIVER BEND.- UNIT 1 3/4 6-19 Amendment No. 4,7, l

1 l

e CONTAINMENT SYSTEMS-DRYWELL AIR LOCKS LIMITING CONDITION FOR OPERATION i

3.6.2.3 The drywell air lock shall be OPERABLE with:

a.-

Both doors closed except that, when the air lock is being used for normal transit entry and exit through the drywell, at least one air lock door shall be closed, and b.

An overall air lock leakage rate of less than or equal to 11.85 scf per hour at 3.0 psid, and c.

The inflatable seal system air flask pressure 3 75 psig.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2*, and 3.

ACTION:

a.

With one drywell air lock door inoperable, maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

Operation may then continue provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the follnwing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With the drywell air lock inoperable, except as a result'of an inoperabie air lock door, maintain at least one air lock door closed;' restore the filoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With one inoperable drywell air lock door inflatable sral syctem air flask j

s pressure instrumentation channel, restore the inoperable channel to OPERABLE status within 7 days or verify air flask pressure to be 3 75 psig at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

j l

See Special Test Exception 3.10.1.

l RIVER BEND - UNIT 1 3/4 6-20 Amendment No. 47 l

CONTAINMENT SYSTEMS 3/4.6.4 PRIMARY CONTAINMENT AND DRYWELL ISOLATION VALVES LIMITING CONDITION FOR OPERATION j

~

3.6.4 The primary containment and drywell isolation valves in Table 3.6.4-1 l

shall be OPERABLE with isolation times less than or equal to those shown in

)

Table 3.6.4-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

1 ACTION:

)

1 With one or more of the primary containment or drywell isolation valves shown in Table 3.6.4-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either:

l a.

Restore the inoperable valve (s) to OPERABLE status, or j

b.

Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isoitted position, and declare the associated system inoperable, if applicable, and perform the assoc-isted ACTION statements for that system,* or c.

Isolate each affected penetratinn by use of at least one closed _ manual valve or blind flange and declare the associated system inoperable, if applicable, and perform the associated ACTION statements for that-system

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS OPERABLE prior to returning the valve to service, after maintenance, repair or 4.6.4.1 Each isolation valve shown in Table 3.6.4 1 shall be demonstrated replacement work is performed on the valve or its associated actuator, control or power circuit, by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.

4.6.4.2 Each automatic isolation valve shown in Table 3.6.4-1 shall be demon-strated OPERABLE during COLD SHUTDOWN or REFUELING at least once per 18 months, by verifying that, on an isolation test signal, each automatic isolation valve actuates to its isolation position.

Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative controls.

The specified 18 month interval during the first operating cycle may be extended to coincide with completion of the first refueling outage scheduled to begin 9-15-87 for those items noted on Table 3.6.4-1.

(=

RIVER BEND - UNIT 1 3/4 6-31 Amendment No. 9, 47

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J C_0NTAINMENT SYSTEMS

.' 19RYPLIANCE REQUIREMENTS-(Continued)

I n.

- 4.6.4.3 The-isolation time of each power operated or automatic valve shown in--

- Table 3.6.4-1 s5all be determined to be within its limit.when tested pursuant-to Specification 4.0.5.

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(RIVER BEND - UNIT 1 3/4 6-31a Amendment No. 9 x,

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3

5 CONTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOMATIC ISOLATION DAMPERS LIMITING CONDITION FOR OPERATION f3.6.5.3 :The secondary containment ventilation system automatic isolation dampers shown.in Table 3.6.5.3-1 shall be OPERABLE y M isolation times less than or equal to the times shown in Table'3.6.5.3.'.

/

APPLICABILITYi As shown in Table 3.6.5.3-1.

ACTION:

]

With one or more nf the secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.3-1 inoperabic, maintain at least.one isolation Jamper OPERABLE.in each affected penetration that is open-and, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , either:

a.-

Restore the inoperable damper (s) to OPERABLE status, or b.

Isolate each-affected penetration by use of at least one deactivated automatic-damper secured in the_ isolation position _and declare the associated system inoperable,-if applicable, and-perform the assoc-iated ACTION statements for that; system, or c.

Isolate each affected penetration by use'of at-least one closed manual-valve or blind flange'and declare the associated system inoperable, if applicable, and p:rform the associated ACTION statements for that system.

Otherwise,.in OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN-within the next 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s-and-in COLD SHUTDOWN within'the following 24' hours.

-s Otherwise, in Operational Condition ##, suspend' handling of-irradiated i

fuel in the Fuel. Building.

The provisions of Specification 3.0.3 are not y

applicable.

l SURVEILLANCE REQUIREMENTd 4.6.5.3-. Each secondary containment ventilation system automatic isolation-damper shown in Table 3.6.5.3-1 shall be demonstrated OPERABLE:

11

. a.

Prior to returning the damper to-service after maintenance, repair or

/

replacement work is performed on the damper or its associated actuator, control or power circuit, by cycling the damper through at least one complete cycle of full travel and verifying the specified isolation time.

1. When irradiated fuel is being handled in the Fuel Building.

g RIVER BEND - UNIT 1 3/4 6-51 Amendment No. 47

"-l W'

t;:

CONTAINMENT SYSTEMS c

}

-SURVEILLANCE REQUIREMENTS (Continted) b.

At least once per 18 months ###, during COLD SHUTDOWN or REFUELING, by verifying.that, on a containment isolation test signal, each isolation:

i damper actuates to-its isolation position.

,E

_c.

_ By verifying the isolation time to be within its limit when tested 4

_ pursuant to Specification 4.0.5.

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1. 1. The.specified.18 month' interval during the first operating cycle may oe extended to coincide with completion of the first refueling outage, scheduled to,begin 9-15-87.

o RIVER' BEND'- UNIT 1 3/4 6-52 Am.endment No. 9,'

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PLANT SYSTEMS SPRAY-AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION t

3.7.6.2 The following spray and sprinkler.. systems shall be OPERABLE:

SYSTEM LOCATION ELEVATION IDENTITY-a.

Control Bldg. Cable Chases 116'0" AS-6A 98'0" AS-6B 70'0" AS-6C, WS-6A, WS-6B, WS-6C 115'0" WS-7A, WS-78 b.

uett Tunnels 67 ' 6"/70 ' 0'!

WS-80, WS-8E, WS-8F, 67'6"/70'0" WS-8G, WS-8H, WS-8K, 67'6"/70'0" WS-8L, WS-8M, WS-8N c.

Auxiliary Bldg., RCIC 70'0" PS-1, WS-19 Pump Room 141'0" WS-4A, WS-48, WS-20, AS-12 d.:

Diesel Generator Bldg.

98'0" PS-2A, PS-28, PS-2C e.

Fuel Bldg.

95'0"

. 5-5

^

148'0" WS-5A, WS-58 APPLICABILITY:

Whenever equipment protected by the spray or sorinkler systems is required.to be OPERABLE.

ACTION:

,a.

With one or more of the above required spray or sprinkler systems

, inoperable, within one hour' establish a continuous fire watch with.'

backup. fire suppression equipment for those areas in which redundant systems or components could be damaged;'fo'r other areas,_ establish an hourly fire watch patrol.

b.

The provisions of Specification 3.0.3 are not applicable.

4 i

RIVER BEND - UNIT 1 3/4 7-21 Amendment No. 47 o

i

'd -,

,p; l PLANT SYSTEMS.

-SURVEILLANCE REQUIREMENTS-4.7.6.2x Each of the-above required spray and sprinkler systems shall be demonstrated OPERABLE:

a.

At least once per 31-days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct 1

position, l

i b.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of ful's travel, j

c.

At least once per 18 months:

1.

By performing a system functional test which includes simulated q

automatic actuation of the automa. tic systems, and:

a)L Verifying that the automatic valvesvin the flow path actuate 4

to their correct positions on a simulated actuation. test signal, and b)

~ Cycling each valve in the flow path, that is-not testable-1 during plant operation, through at least one complete ~ cycle

.of full travel.

2.

By a visual inspection of the. dry pipe spray and sprinkler heaocrs to verify their integrity.

3.

-By a visual inspection of each deluge nozzle's spray area *,to verify that the -spray pattern is not obstructed.

d.

At least-once per 3 years by performing an air or water flow test through each open head spray and sprinkler htader system

and l

verifying that-each open head spray nozzie and sprinkler header system is unobstructed.

I I

l

^The charcoal filter system spray nozzles need only be visually inspected and

. verified to be unobstructed each time the charcoal is changed.

RIVER BEND - UNIT 1 3/4 7-22 l

1

1 1

PLANT SYSTEMS.

HALON SYSTEMS LIMITING CONDITION FOR OPERATION-q

~3.7.6.3 The following main control room Power Generation Control Complex (PGCC)-

Halon systems shall be OPERABl.E with the storage tanks havinggat least 95% of full charge weight and 90% of full charge pressure:

PGCC Panel Module U701 PGCC Panel Module 0730 PGCC Panel Module V702 PGCC Panel Module V731' PGCC Panel Module U703 PGCC Panel Module U732 PGCC Panel Module V704 PGCC Panel Module U740 PGCC Panel Module U710 PGCC Panel Module V741 PGCC Panel Module U711 PGCC' Panel Module U742 PGCC Panel Module U712 PGCC Panel Module U743-PGCC Panel Module V713 PGCC Panel Module.U744

't PGCC Panel Module U714 PGCC Panel Module.U745 t

PGCC Panel Module U715 PGCC Panel Module V746:

PGCC Panel Module U717 PGCC Panel Module V747 PGCC Pane 1' Module U720 PGCC Panel Module V748 PGCC Panel Module U721 PGCC Panel Module V799-PGCC Panel Module U723 PGCC Panel Module V750 APPLICABILITY:. Whenever equipment protected by the Halon systems is. required to be OPERABLE.

ACTION:

a.

With one or more of the above required Halon systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression v

zequipment for those areas in which redundant systems or components coulti be damaged; for other areas. establish an hourly fire watch patrol.-

b.

The provisions of Specification 3.0.3'are not applicable, SURVEILLANCE REQUIREMENTS I

.4.-7.6.3 The above required Halon system shall-be demonstrated 0P'ERABLE:-

g,

a.

At least once per 31 days by verifying that each Halon system storage tank is pressurized to at least 280 psig.

- b.

At least once per 6 months by verifying Halon storage tank weight and pressure, i

!b RIVER BEND - UNIT 1 3/4 7-23 Amendment No.47 i h&

~

j e

. PLANT SYSTEMS;

)

J

'l SURVEILLANCE REQUIREMENTS (Continued) c.;

At least once per 18 months by:

'1.

Verifying the system actuates, manually and automatically, upon receipt of a simulated actuation signal (actual HalonTrelease, i

Halon bottle initiator valve actuation, and electro-thermal link

. burning may be excluded from the test), and t

2.

Performance of a flow test through headers and nozzles to assure no blockage.

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I RIVER BEND - UNIT,1 3/4 7-24 o

- 5 '-

n 4

.z.

PLANT SYSTEMS-

- FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.6.4 The fire-hose stations shown in Table 3.7.6.4-1 snell be OPERABLE.

APPLICABILITY: Whenever equipment'in the areas protected by the fire hose stations-is required to be OPERABLE.

ACTION:

a.

With one or more of the fire hose stations shown in Table 3.7.6.4-1 inoperable, provide gated wye (s) on the nearest-0PERABLE hose station (s).

One outlet of the wye shall be connected to the standard length of hose provided for the hose station.

The second outlet of the-wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station.

Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to operating technicians, plant equipment, or the hose itself, the fire hose shall be stored in a roll at the outlet of the OPERABLE hose station.

Signs shall be mounted above the gated wye (s) to identify the proper hose to use.

The above ACTION shall be accomplished within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; other-wise. route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS

' 4.7.6.4= Each of the fire hose stations shown in Table 3.7.6.4-1 shall-be demonstrated OPERABLE:

a.-

At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operation to assure all required equipment is at the station.

.b.

At least once per 18 months by:

1.

Visual inspection of the fire hose stations not accessible during plant operation to assure all required equipment is at the station.

2.

Removing the hose for inspection and re-racking, and 3.

Inspecting all gaskets and replacing any *: graded gaskets in the couplings, i

RIVER BEND - UNIT 1 3/4 7-2b Amendment No. 47

1 I

.- - 4

' PLANT SYSTEM.S.:

a.

. SURVEILLANCE REQUIREMENTS (Continued)-

i c..

-At least once per 3. years by:

~-t'i 11.~

. Partially opening each hose station valve to verify valv2 OPERABILITY and no-flow blockage.

g

.- t 2.

Conducting a hose hydrostatic. test at a pressure of-150 psig or;

~.

at-least 50 psig above-the maximum. fire main' operating pressure, q

i st whichever-is greater.

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l RIVER ~ BEND - UNIT 1 3/47-2i

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hl,, lf TABLE 3.7.6.4-1 wK,.

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. FIRE HOSE' STATIONS.

ll; CD ie &

HOSE RACK 7~"

LOCATION-ELEVATION INDENTIFICATION-

/

M, a.

Rear. tor Building

. 114'0" HR - 16,:22.

-141'0" HR.- 17, 23

.162'3" HR - 18,-19, 24, 25 l

186'3" HR - 20, 21, 26 b.

Auxiliary Building 70'0"'(Stairwell)

HR - 84

-j 95'9" HR - 6, 7, 8, 9 t

114'0" HR - 10,:11.

141'0"

' HR - 12, 13, 14,- 15.

-170'0"~

HR c.

Control _ Building 70'0"-

-HR~-'85, 86, 87 98'0"

= HR - 88, ~89, 90 r

-115'0" and 116'0" HR - 91, 92, 93, 94 -

135'0" (Stairwell)

HR - 96.

d.

Fuel Building 70'0" HR - 1, 2, 82 :

95'0" HR - 3, 4 113'0" HR.- 81.

148'0"-'

HR - 5

-l e.

Pipe Tunnel 67'6" HR

'83-

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f.1. Turbine' Building 95'0" HR - 50, 51 l

123'6" HR-- 53 l

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RIVER BEND.- UNIT.1 3/4 7-27 r

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. PLANT SYSTEMS

~

4 YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES LIMITING CONDITION ~FOR OPERATION j

3.7.6.5 The yard fire hydrants and associated hydrant hose houses shown in

Table-3.7.6.5-1 shall be OPERABLE.

APPLICABILIlY:

Whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE.

i ACTION:

a.

With one or more of the yard fire hydrants or associated hydrant hose houses shown in Table 3.7.6.5-1 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months have sufficient additional lengths of 21/2 inch diameter hose located in an adjacent OPERABLE hydrant hose house to provide service to the unprotected area (s) if the inoperable fire hydrant or associated-y hydrant hose house is the primary means of fire suppression-i otherwise provide the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i b.

The provisions of Specification 3.0.3 are not applicable. -

)

i SURVEILLANCE REQUIREMENTS i

4.7.6.5 Each of the yard fire hydrants and associated hydrant hose houses

?

shown in Table 3.7.6.5-1 shall be demonstrated OPERABLE:

a.

At least once per 31 days by visual inspection of the hydrant hose house to assure all required equipment is at the hose house.

6 b.

At least once per 6' months, by visually inspecting each yard

- fire hydrant and verifying that the hydrant barrel is dry and l

that the hydrant is not damaged.

1 c.

At least once per 12 months by:

1.

Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater.

2.

Replacement of all degraded gaskets in couplings.

3.

Performing a flow check of each hydrant, t

RIVER BEND - UNIT 1 3/4 7-28 Amendment No. 47 l

l 4

TABLE-3.'7.6.5-11

YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES-LOCATION.

HYDRANT-NUMBER'

a Northeast'of Fuel' Bldg FHY 11L

b. -

East of Control. Bldg _

FHY 13 c.

West of Standby Cooling Tower

'FHY 9*-

4 d.

North of Fue1< Bldg FHY 10' 1

s 1

1 t

No associated hose house.

RIVER BEND - UNIT 1 3/4 7-29 o.

+

1 PMNT. SYSTEMS

- 3/4.7.7 FIRE-RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.7 All' fire barrier assemblies shall be OPERABLE.: Fire barrier assemblies g

- include:

a.

Walls, floors / ceilings, cable' tray enclosures, and other fire barriers that separate safety-related fire areas or that separate portions of' redundant systems, important to safe shutdown, within a fire area, and b.

All. sealing ~ devices in fire rated assembly penetrations, including-fire doors -and~ fire-dampers' and cable,' piping and ventilation duct.

penetration seals, and ventilation seals.

o

' APPLICABILITY:

At all times.

ACTION:

a.

With one or more of the above required fire-rated assemblies or sealing devices inoperable, within l' hour establish a continuous

. fire watch on at_least one side-of the affected assembly and/or sealing devie.e or verify the OPERABILITY of fire detectors = on at least one side of the inoperable assembly:or sealing device,cand establish an hourly fire watch patrol.-

.b.-

The, provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 2

s

4. 7. 7.1-Each of'the above' required fire-rated assemblies and penetration-

' sealing devices shall be verified OPERABLE at least once per 18 months by performing a visual inspection of:

-a.-

The exposed surfaces of each' fire-rated assembly.

b.

Each fire damper and associated hardware.

c.

'At least 10 percent of each type of sealed penetration.

If changes in appearance or abnormal degradations are found, a visual inspection' of an additional 10 percent of each type of sealed penetration shall be made.

This inspection process shall continue until a 10 percent s

sample is found with no apparent changes in appearance or abnormal degradation.

Samples shall be selected such that each penetration

~

seal will be inspected at least once per 15 years.

l RIVER BEND - UNIT 1 3/4 7-30 Amendment No. 47 t

i

' eJ PLANT SYSTEMS

' 3/4;7.10 STRUCTURAL SETTLEMENT LIMITING CONDITION FOR OPERATION 3.7.10 Structural. settlement shall be within the predicted values as shown in '

Table 3.7.10-1 and calculated differential settlements shall be within the allowabla' ranges shown in Table 3.7.10-2 for the following structures:

a.

Reactor Building b.

Auxiliary Building j

c.

Fuel Building d.

Control Building e.

Diesel Generator Building f.

Standby Cooling Tower, Basin and Pump House

g..

BF Tunnel h.

Main Steam Tunnel i.

E Tunnel 1

G Tunnel APPLICABILITY:

At all times.

ACTION:

1

- With the measured structural settlement of cny of the above required structures I

outside of the limits of Tables 3.7.10-1 and 3.7.10-2, prepare and submit, within the,next 30 days, a Special Report to the Commission, pursuant to Specification 6.9.2, providing a record of the settlement measurements and the predicted settlement', an analysis to demonstrate the continued structural integrity of the affected structure (s), and plans to monitor the settlement of the affected structure (s) in the future.

The provisions of Specification 3.0.3 are not applicable to the limits established in-Table 3.7.10-1.

' SURVEILLANCE-REQUIREMENTS I

4.7.10 'The structural settlement of the above required structures shall be demonstrated to be within.the limits of Tables ~3.7.10-1.and 3.7.10-2:

a.

At least once per 92 days, until there is essentially no movement during those 92 days, b.

At least once per 24 months, for at least 10 years.

a:

c.

-Following any seismic event equal to or greater than an Operational Basis Earthquake (OBE).

I

'h RIVER BEND - UNIT 1 3/4 7-35 Amendment No. 47 a

h a

1 L

TABLE 3.7.10-1 s

TOTAL PREDICTED' SETTLEMENTS OF MAA R STRUCTURES SETTLEMENT PREDICTED STRUCTURE MARKER NO.

SETTLEMENT (IN.)

Reactor Building--

15 4.0^

./.;'

16 4.0 17 4.0 Auxiliary Building 18 3.8 19 3.6 20 3.9 21 3.7 I

Fuel: Building-11 3.7 12' 4.0 13

3. 5 14 3.8 1

- Control Building 5

3.7 1

6 3.3 7

3.7 8

3.7 j

i Diesel Generator Building 1

3.4 2

3.7 3

3.6

-4 3.8 ;

Standby Cooling _-Tower,: Basin 30

'2.7__

- )

and Pump House 31 3.2'-

32 2.4.

BF Tunnel 9

2.1' 10 2.5-

'i Main Steam Tunnel 22 3.8 1

23 3.8 j

E Tunnel 28 3.3 29 2.8 G Tunnel 33 2.6L 34 1.3

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. RIVER BEND - UNIT 1 3/4 7-36 Amendment No.

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a' ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL' EQUIPMENT PROTECTIVE DEVICES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION t

1 3.8.4.1 All primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.1-1 shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

' ACTION:

With one or more of the primary containment penetration conductor overcurrent

. protective devices shown in Table 3.8.4.1-1 inoperable, declare the affected i

system or component inoperable and apply the appropriate ACTION statement for the affected system and:

a.

For 4.16 kV circuit breakers, de-energize the 4.16 kV circuit (s) by tripp ;

ing the associated redundant circuit breaker (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify-ing, at least once per,7 days thereafter, the redundant circuit: breaker to be tripped, b.

For 480 volt circuit breakers,-remove the inoperable circuit breaker (s) from service by racking out the breaker within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verifying, at least once per 7 days thereaf ter, the inoperable breaker (s) to be racked

out, c.

For 480 volt MCC circuit breaker / fuse combination starters, remove the inoperable starter (s) from service by locking the breakers open and remov--

ing the control power fuse within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verifying, at least once per 7: days thereafter, the inoperable starter (s) circuit breaker to be locked open with the control power fuse removed.

d.

For 120/140 volt molded case circuit breakers, remove the inoperable cir-1 cuit breaker (s) from service by-tripping both 120/140 volt breakers open and locking the upstream 480 volt MCC breaker open within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verifying, at least once per 7 days thereaf ter, the 480 volt MCC breaker (s) to be locked open.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

RIVER BEND - UNIT 1 3/4 8-25 Amendment No. 47

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E'LECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.4.1. Each of:the primary containment penetration conductor overcurrent protective devices shown'in Table 3.8.4.1-1 shall be demonstrated OPERABLE:

a.

At least once per.18 months:

1.

.By verifying that the medium voltage 4.16 kv circuit breakers are OPERABLE by selecting, on a rotating basis, at least one of the four circuit breakers and performing:

-a)

A CHANNEL CALIBRATION of the associated protective' relays, and' b)

An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay-and associated circuit breakers and overcurrent control i

circuits function as designed.

d=

<c)

For each circuit breaker found inoperable during these functional' i

tests, an additional representative sample-of at least one 11 l

of the>four circuit breakers of the inoperable type shall' also be functionally tested until no more failures are found or all circuit breakers of'that type have been' functionally U]

tested.

9 2.

By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.

Circuit breakers' selected for functional testing shall be selected on a rotating' basis.

Testing of these' circuit breakers shall I

consist of injecting currents in excess of the breaker's nominal setpoint and measuring the response time of the long time'and short time delay elements and the.setpoint of the instantaneous element,1 as appropriate.

The measured data shall-be compared

.j to the manufacturer's data to ensure that it is less than or equal to a value specified by:the manufacturer.

Circuit breakers j

found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. -For each circuit breaker found inoperable during these functional tests, an addi-

.l tional representative sample.of at least 10% of all the circuit breakers of the inoperable type shall also be functionally. tested unti1~no more failures are found or all circuit breakers of that type have been functionally tested.

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w RIVER' BEND - UNIT 1 3/4 8-26 i

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4 ELECTRICAL POWER SYSTEMS

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.0THER OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION i

j 3.8.4.2 The overcurrent protection devices shown in Table 3.8.4.2-1 shall be i

OPERABLE.

-l APPLICABILITY:

At all times.

ACTION:

r With one or_more of the overcurrent protective devices shown in Table 3.8.4.2-1

-inoperable, remove the circuit breaker (s) feeding the control room lighting and/

or alternate RPS supply as appropriate from service by opening the breaker (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and return the overcurrent protection devices to OPERABLE status within 7 days, or verify the appropriate breakers open at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .*

SURVEILLANCE REQUIREMENTS 4.8.4.2 The overcurrent protective devices shall be demonstrated OPERABLE at.least once per 18 months by selecting and testing one-half of-each type of circuit breaker on a rotating basis.

Testing of these circuit breckers shall consist of injecting currents in excess of the breaker's nominal setpoint.

and measuring the response time of the long time and short time delay elements =

and the setpoint of the instantaneous element, as appropriate. _The measured data shall.be compared to the manufacturer's data to ensure that it is less than or_ equal to a value specified by the manufacturer.

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Except at least once per 31 days if locked, sealed, or otherwise secured in the open position.

RIVER BEND - UNIT 1 3/4 8-33 Amendment No. 47~

-TABLE 3.8.4.2-1 i

OTHER OVERCURRENT PROTECTIVE DEVICES l

TYPE 1,

Main Control Room Lighting Protective Device 1EHS*MCC14A 1EHS*MCC14B j :.

2.

RPS Alternate Source of Power Primary Protect' ion.

Secondary Protection l.

1EHS*MCC14A 1RPS*XRC10A 1EHS*MCC14B 1RPS*XRC10B 1

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' RIVER: BEND - UNIT 1 3/4 8-34

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REFUELING OPERATIC,NS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL

. LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and in operation

with at-least:

a.

One OPERABLE RHR pump, and b.

Two OPERABLE RHR heat exchangers.

APPLICABILITY:

OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is greater than or equal to 23 feet above the top of the reactor pressure vessel flange.

ACTION:

.a.-

With no RHR shutdown cooling mode OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal.

Otherwise, suspend al.1 operations involving an increase in the reactor decay heat load and establish PRIMARY CONTAINMENT INTEGRITY - FUEL HANDLING within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

With no-RHR shutdown cooling mode loop in operation, within one hour

-establish reactor coolant circulation by an1 alternate method, and monitor-reactor coolant temperature at least once per hour.

SURVEILLANCE REQUIREMENTS' 4.9.'11.1 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be verified, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , to be in operation and circulating reactor coolant.

"The shutdown cooling loop may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per-8-hour period.

RIVER BEND

-UNIT 1 3/4 9-17 1

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.N REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.2 Two shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and at least one loop shall be in operation,* with

- each train consisting of at least:

a.

One OPERABLE RHR pump, and I

b.

Two OPERABLE RHR heat exchangers.

APPLICABILITY:

OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is less than 23 feet abcve the top of the reactor pressure vessel flange.

l ACTION:

a.

With dess than the above required shutdown cooling mode loops of the RHR systs1 OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay. heat removal for each inoperable RHR shutdown cooling mode train.

. b.

With.no RHR. shutdown cooling mode loop in operation, within one hour establish reactor' coolant circulation by an alternate method, and monitor reactor coolant temperature at least once per hour.

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'i SURVEILLANCE REQUIREMENTS J

4.9.11.2. At least one shutdown cooling mode loop of the residual heat' removal

- system or alternate method shall be verified, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , to be in operation and circulating reactor coolant, i

"The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8-hour period.

RIVER BEND - UNIT 1 3/4 9-18 Amendment No.

26, 47

TABLE 4.11.1.1.1-1 (continued)

TABLE NOTATION (continued) s is the standard deviation of the background counting rate or of the b

counting rate of a blank sample, as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement, b-A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

c-The principal gamma emitters for which the LLD specification applies exclu-sively are the following radic?uclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.

This list ooes not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

d-A composite sample is one in which the quantity of liquid sampled is propor-tional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

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RIVER BEND - UNIT 1 3/4 11-3

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~RADI0 ACTIVE EFFLUENTS DOSE-LIMITING CONDITION FOR OPERATION

-i 3.11.1.2 The: dose or dose commitment to a MEMBER OF THE PUBLIC from radio '

s active materials in liquid effluents released to-UNRESTRICTED AREAS-(see i

Figure _5.1.3-1)_shall be limited:

a.

During-any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and b.

During any calendar year to less than or equal-to 3 mrems to the.

total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY:

At all times.

' ACTION:

a.-

With the calculated dose, from the release of radioactive materials.

in liquid effluents, exceeding any of the above limits,-prepare and submit to the Commission within 30 days, pursuant to Specifica-

-tion 6.9.2, a Special Report that identifies the cause(s) for' exceeding the limit (s) and' defines the corrective actions that have been taken-

.to reduce the releases and the proposed corrective actions to be taken to. assure that subsequent releases will be -in compliance with the above limits, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS L

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-_4.11.1. 2 Cumulative dose contributions from liqr f effluents _for the current, calendar quarter and the' current calendar year shall be determined, at least l

once per 31 days, in accordance with the methodology and parameters in the ODCM.

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1 l-RIVER BEND UNIT 1 3/4 11-4 Amendment No. 47 l

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Ri.i10 ACTIVE EFFLUENTS!

LIQUID RADWASTE TREATMENT SYSTEM LIMITING-CONDITION FOR OPERATION g

i 3.11.1.3 The liquid'radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses,=due to the liquid. effluent, to UNRESTRICTED. AREAS'(see Figure 5.1.3-1) would exceed 0.06 mrem to the total body or 0.2 mrem to'any 3

organ.in a 31' day period, l

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= APPLICABILITY:

At all times.

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. ACTION:

t a.

With radioactive liquid waste being discharged without~ treatment and in excess of.the above limits, prepare and submit to the Commission within 30 days,-pursuant to Specification 6.9.2, a Special Report that includes the following information:

1..

. Explanation of why liquid radwaste was being' discharged without' O

. treatment,sidentification of any inoperable equipment or l-subsystems,.and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable' equipment to 0PERABLE status, and 3.

' Summary description of action (s) taken to' prevent a recurrence.

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The provisions of Specification 3,0;3 are not' applicable, p

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' SURVEILLANCE REQUIREMENTS j

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4.11.1.3: Doses due to liquid releases to. UNRESTRICTED AREAS shall be projected at least'once.per 31 days in accordance with the methodology and' parameters in the 0DCM.

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RIVER BEND - UNIT 1 3/4 11-5 Amendment No. 47 j,

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.RADICACTIVE EFFLUENTS LIQUID HOLDUP 1 TANKS LIMITING CONDITION FOR'0PERATION 3.11.1 4 The quantity of radicactive material contained in any unprotected.

_ outdoor tank shall be limited to ies: than or equal to 10 curies, excluding

-tritium and dissolved or entrained noble gases.

3, APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above unprotected outdoor tanks exceeding the above limit, immediately-suspend all additions of radioactive material to the tank; witnin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to'within the limit; and describe the events leading to this condition in the next Semiannual Radio-active Effluent Release Report.

b.

The provisions of Specifications 3.0.3-and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4-The quantity of radioactive material contained in each o'f the abo'/e unprotected outdoor tanks shall be determined to be within the above-!imit by1 analyzing a representative-sample of the tank's. contents at least once per 7 days when radioactive materials are being.added to the tank.

I RIVER BEND - UNIT 1 3/4 11-6 n =

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RAD 10 ACTIVE' EFFLUENTS' J.

00SE - NOBLE GASES

LIMITING CONDITION FOR OPERATION 1

3.11.2.2' The air _ dose due to noble' gases released in' gaseous effluents to-I areas at and beyond the SITE BOUNDARY (see-Figures 5.1.1-1 and 5.1.3-1) shall be limited to the-following:

q a.

During any calendar' quarter:

Less_than or equal to 5 mrads for gamma-radiation and less than or equal to 10 mrads for beta radiation and,._

T b.

During any calendar year:

Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated air dose from radioactive noble-gases in gaseous effluents exceeding any of the'above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, I

a Special Report that identifies the cause(s)_for exceeding the limit (s)'and defines the corrective actions that have been taken to reduce the release's and the proposed corrective actions to be taken to assure that. subsequent releases will be in compliance with the above limits.

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I b..

-The provisions of Specification 3.0.3 are not applicable.

1 SURVEILLANCE REQUIREMENTS F

4.11.2.2 At least once-per 31 days, cumulative' dose contributions for the cur-

'I rent calendar quarter and current calendar year for noble gases shall-be~ deter-mined"in accordance with the' methodology and parameters _in the ODCM.

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' RIVER BEND -' UNIT 1 3/4 11-11 Amendment No. 47 g._

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1 RADI0 ACTIVE EFFLUENTS DOSE - 10 DINE-131, 10 DINE-133, TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater; than 8 days, in, gaseous eff~luents released to areas at and beyond the SITE BOUNDARY (see Figures 5.1.1-1 and 5.1.3-1), shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 7.5 mrems to any organ and, b.

During-any calendar year:

Less than or equal to 15 mrems to any t

organ.

APPLICABILITY:

At'all times, s

. ACTION:

a.

With,the calculated dose from the release, in gaseous' effluents, of iodine-131,~ iodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days, exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant-to Specification 6.9.2, a Special Report that identifies.the cause(s).

for exceeding the limit and defines the corrective actionsm that have been taken to reduce'the releases and the proposed corrective actions to be taken to assure that. subsequent releases will-be-in compliance with the above limits.

b.

The-provisions of-Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4

4.11.2.3 At least once per 31 days, cumulative dose contributions for the cur-rent calendar quarter and current calendar year for iodine-131, iodine-133,

- tritium,- and radionuclides in particulate form with half lives greater than 8 days,~shall be determined'in accordance with the methodology and parameters in the ODCM.

.i RIVER BEND -' UNIT 1 3/4 11-12 Amendment No. 47

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RADIOACTIVE EFFLUENTS

--GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT (0FFGAS) SYSTEM shall be in operation.

APPLICABILITY:- Whenever the main condense? air-ejector system is jn operation.

l ACTION:

-a.

With GASE0US RADWASTE TREATMENT (0FFGAS) SYSTEM inoperable for more

't than 7 days, prepare and submit to the Commission within-30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1.

Identification of the. inoperable equipment or subsystems and the reason for inoperability, 2.

-Action (s) taken to restore the inoperable equipment to OPERABLE-4

-status, and 3.-

Summary description of action (s) taken to prevent recurrence.

b..

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The instruments specified in:the ODCM shall be checked every.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , whenever the main condenser air ejector is in operation, to ensure that the GASE0US RADWASTE TREATMENT (OFFGAS) SYSTEM is functioning.-

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RIVER BEND - UNIT 1 3/4 11-13 Amendment No. 47

3 Rj010ACTIVEEFFLUENTS VENTILATION EXHAUST TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, dut to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Figures 5.1.1-1 and 5.1.3-1), would exceed 0.3 mrem to any organ in a 31 day period.

APPLICABILITY:

At all times other than when the VENTILATION EXHAUST TREATMENT system is undergoing routine maintenance.

ACTION:

a, With gaseous waste being discharged from the ventilation exhaust ducts without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that includes the following information:

1.

Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipnant or sub-systems, and t5e reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

lne provisions of Specification 3;0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 Doses due to gaseous releases from the site shall be projected at l'

least once per 31 days in accordance with the methodology and parameters in the 00CM.

RIVER BEND - UNIT 1 3/4 11-14 Amendment No. 47 i

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RADI0 ACTIVE EFFLUENTS

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3/4.11.3 SOLIDRADIDACTJVEWASTE LIMITING CONDITION FOR OPERATION l

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- 3.11.3 The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial i

ground requirements.

APPLICABILITY: At all times, i

l ACTION:

a.

With the. provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectivelv processed or defectively packaged solid radioactive wastes from the site.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS i

4.11.3 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each. type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, sodium sulfate solutions).

l a.

If any to>: specimen fails.to verify SOLIDIFICATION, the SOLIDIFICA-TION of the batch under test shall be suspended until such time 's additional. test specitens can be obtained, alternative'SOLIDIFI"ATION parameters can be determined in accordance with the PROCESS CONTROL i

PROGRAM, and a subsequent test verifies SOLIDIFICATION.

SOLIDIFICA-TION of the batch may then be resuaed using the alternative SOLIDIFI-CATION parameters determined by the PROCESS CONTROL PROGRAM.

b.-

If the initial test specimen from a batch of watte faj)s to'verif; SOLIDIFICATION, the PROCESS CONTROL PROGRAM shel) provide for the collection and testing of representative tEtt specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonst. rate SOLIDIFICATION.

,The PROCESS CONTROL PROGRAM shall be modiffe4 ts required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent bat:@es i

of waste.

RIVER BEND - UNIT 1 3/4 11-17 Amendment No. 47 e

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RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR.0PERATION 3.11.4 The annual (calendar year) dose or dose commitawnt to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiatioh from uranium fuel cycle sources,-shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which sha*.1 be limited to less than or equal to 75 mrems.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 3.11.1.2.a. 3.11.1.2.b 3.11.2.2.a. 3.11.2.2.b, 3.11.2.3.a. or 3.11.2.3.b. calculations should be made, including direct radiation contributions from the reactor units c.nd from outside storage tanks, to determine whether the above limits of Specification 3.11.4 have been exceeded.

If such is the case, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report l

that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and that includes the schedule for achieving conformance with the above limits.

This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes 4

the releace(s) covered by.this report.

It shall also describe levels of radiation and concentrations'of ra,octive material involved.

and the.cause of the exposure levels or concentrations.

If the-estimated dose (s) exceeds the above limits and, if the release condi-tion resulting in violation of 40 CFR Part'190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.

Submittal of l

-the report is considered a timely request, and a variance is granted j

until staff action on the request is complete.

b.

The provisions of Specification 3.0.3 are not applicable.

SUPVEILLANCE REQUIREMENTS P

d 4.11'.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3 and in accordance with the methodology and parameters in the ODCM.

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4.11.4.2 Cumulative dose contributions from direct radiation from the reactor l

unit and from any unprotected outdoor storage tanks shall be determined in actordance with the methodnlogy and parameters in the ODCM.

This requirement h.

is Applicable only under conditions set forth in Specification 3.11.4, Action a.

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RIVER BEND - UNIT 1 3/4 11 Amendment No. 47 J.

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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring pregram shall be conducted as specified in Table 3.12.1-1.

APPLICABILITY:

At all times.

ACTION:

a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to

]

the Commission, in the Annual Radiolog' cal Environmental Operating l

Report required by Specification 6.9.1.7, a description of the reasons for not conducting the progran as required and the plans for preventing a recurrence, b.

With the level of radioactivity, as the result of plant effluents, in an environmental sampling medium at a specified loc;. tion exceeding i

the reporting levels of Table 3.12.1-2 when averageo over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report tnat identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

to A MEMBER OF THE PUBLIC is less than the calendar year limits of Specificat.ons 3.11.1.2, 3.11.2.2, and 3.11.2.3.

When more than one

~

of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration Q1 concentration

~(2)

+ ***> 1.0 reporting level (1) reporting level (2)

When radionuclidec cther than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

to A MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c.

With milk or broad leaf-vegetation ramples. unavailable from one or more of the sample locations required by Table 3.12.1-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

The

The methodology and parameters used to est' mate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

l RIVER BEND - UNIT 1 3/4 12-1 L

RADIOLOGICALENVIRONMENTALMONITORIKg LIMITING CONDITION FOR OPERATION (Cont?nued)

ACTION:

(Continued) specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant ta Specification 6.9.1.8, identify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samplet in the next Semi-ai.nual Radioactive Effluent Release Report and in.lude in the report a revise:8 figure (s) and table for the 00CM reflecting the new location (s).

d.

The provisions-of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capat,111 ties required by Table 4.12.1-1.

1 RIVER BEND - UNIT 1 3/4 12-2 Amendment No. 47

4 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location, in each of the 16 meteorological sectors, of the nearest milk animal, the r.asmt residence and the nearest garden

of greater than-50 m2 (500 fts) producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

a.

= With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated _in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant-to Specification 6.9.1.8.

b.

With land use census identifying a l'c:ation(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being i

obtained in accordance with Specification 3.12.1, add the new loca-tion (s) to the radiological environmental monitoring program within 30 days.

The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s),

via the same exposure pathway, may be deleted from this monitoring

. program after October 31 of the year in which this land use census

.was conducted.

Pursuant to Specification 6.9.1.8, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and include in the report a revised figure (s) and table for the 00CM reflecting the new location (s).

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c.

The provisions of Specification ~3.0.3 are not' applicable.

SURVEILLANCE REQUIREMENTS

'4.12.2 At least once per 12 months, the land use census shall be co.'.d,0ted L

during the growing season, using that information that will-provide the best l.

results, such as by a door-to-door survey or aerial survey or by consulting local agriculture authorities.

The results of the land use census shall be included,in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

In lieu.of the garden census, broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site bnundary in each of two different direction sectors with the highest predicted D/Qs. Specifications for broad leaf vegetation sampling in Table 3.12.1-1, 4c shall be followed, including analysis of control samples.

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L RIVER BEND - UNIT 1 3/4 12-13 Amendment-No. 47

I RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials, that correspond to samples required by Table 3.12.1-1, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY:

At all times.

ACTION:

a.

With analyses not being performed as required above, report to the l

Commission, in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7, the corrective actions taken to prevent a recurrence.

I b.

The pravisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS

.i i

4.12.3 The Interlaboratory Comparison Program shall be described in the 00CM.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

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RIVER BEND - UNIT 1 3/4 12-14 Amendment No. 47

~

l 3/4.0 APPLICABILITY

[ASES Specifications 3.0.1 through 3.0.4 establish the general requirements applicable to Limiting Conditions for Operation.

These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10CFR50.36(c)(2):

" Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility.

When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL CONDITIONS or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.

The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not mat.

It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or component (s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

There are two basic types of ACTION requirements.

The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements.

In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met.

The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met.

This time limit is the allowable outage time to restore an inoperable system.or component to OPERABLE status or for restoring parameters within_specified '*mi.s.

If these actions are not completed within the allowable outage time limits, e shutdown is required to place the' facility in.an OPERATIONAL CONDITION or other specified condition in which the specification no longer applies.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met.

The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems.

Individual specifications may include i

a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed.

When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new specification becomes applicable.

In this case, the time limits of the ACTION requirements would apply from the point in time that 4

the new specification become, applicable if the requirements of the Limiting Condition for Operation are not itet.

RIVER BEND - UNIT 1 B 3/4 0-1 Amendment No. 47 l

r t

APPLICABILITY

' BASES Specification 3.0.2 establishes that noncompliance with a specification ex4ts when the requirements of the Limiting Condition for Operation are not met and the associated ACTION requiraments have not been implemented within the specified time interval.

The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Specification 3.0.3 establishes the shutdow ACTION requirements that must be implemented when a Limiting Confition for Operation is not t.;t and the condition is not specifically addr;ssed by the associated ACTION.'equirements.

The purpose of this specificatien is to delineate the tima limits for placing the unit in a safe shutdown CONDITION when plant operation cannot )e maintained within the limits for safe operation defined by the Limiting Conaitions for Operation and its ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary removaa of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

One hour is allowed to prepare fo; an orderly shutdown before initiating a change in plant operation.

This time permits the operator to coordinate the reduction in electrical generation with the lead dispatcher to ensure the stability and availability of the electrical grid.

The time limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE.

This reduces thermal stresses on components of.the primary coolant system and the potential for a plant upset that could

-challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated.

The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation.

Therefore, the shutdown may be terminated if the ACTION requirements i

have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER OPERATION.

If the plant is in a lower CONDITION of operation when a shutdown is required, the time limit for reaching the next lower CONDITION of operation applies.

However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced.

For example, if STARTUP is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if remedial measures are completed that would permit a return to POWER OPERATION, l

a penalty is not incurred by having to reach a lower CONDITION of operation in less than the total time allowed.

RIVER BEND - UNIT 1 B 3/4 0-2 Amendment No.

(Z, 47 l

1 I

L

I i

APPLICABILITY BASES The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into an OPERATIONAL CONDITION or condition of -

operation for another specification in which the requirements of the Limiting Condition for Operation are not met.

If the new specification becomes applicable

'in less time than specified, the difference may be added to the allowable outage time limits of the second specificat. ion.

However, the allowable outage time limits of ACTION requirements for a higher CONDITION of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower CONDITION of operation.

i The shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification 3.0.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition,'or Oftration is not met.

It precludes placing the facility in a higher CONMTION f operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to-comply with the ACTION requirements if.a change in CONDITIONS were permitted.

The purpose of this specification is to ensure that facility operation is not initiated or that i

higher CONDITIONS of operation are not entered when corrective action is being

.taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits.

Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPERATIONAL CONDITIONS.

Therefore, in this case, entry into an OPERATIONAL CONDITION or other specified condition may be made provided the ACTION requirements are being complied with exclusive of the allowable outage time limits.

The provisions of this specification should not, howevor, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because.they would delay placing the facility in a lower CONDITION of operation, i

Specifications 4.0.1 through 4.0.5 establish the general requirements 1

applicable to Surveillance Requirements.

These requirements are based on the Surveillance Rt.quirements stated in the Code of Federal Regulations, 100FR50.36(c)(3):

" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."

RIVER BEND UNIT 1 B 3/4 0-3 Amendment No. 47

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APPLICABILITY BASES Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL CONDITIONS or other conditions for which the 4

L requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual. Surveillance Requirement.

The purpose of this i-specification is to ensure that surveillances are performed to verify the l

operational status of systems and components and that parameters are within j

specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition-for which the individual Limiting Conditions for Operation are applicable.

Surveillance Requirements I

do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The Surveillance Requirements L

associated with a Special Test Exception are only applicable when the Special i

L Test Exception is used as an allowable exception to the requirements of a

)

specification.

5pecification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended.

Item a. permits 1

an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

Item b. limits the use of the provisions of item a to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified.

The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of I

conformance with the Surveillance Requirements.

These provisions are sufficient l

to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance l

interval.

i l

Specification 4.0.3 establishes the failure to perform a Surveillance Requ;rement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requireme%s have been satisfactorily performed within the specified time 4t:nal.

However, nothing in this provision is j

1 to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.

This specification also clarifies that the ACTION requirements

.are applicable when Surveillance Requirements have not been completed within i

the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this-does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for RIVER BEND - UNIT 1 B 3/4 0-4 Amendment No. 47

I APPLICABILITY-

. BASES i

Operation that is subject to enforcement action.

Further, the failure k l

perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(B) secause it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay 3

in implementing the ACTION requirements.

This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before.other remedial measures would be required that may preclude the completion of a.

surveillance.

The basis for this allowance includes consideration for plant j

conditions, adequate planning, availability of personnel, the time required to

.I perform the surveillance and the safety significance of the delay in completing.

the required surveillance.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time.

When a surveillance is performed within the 24-hour allowance and the Surycillance Requirements are not met, the time h nits of the ACTION I

requirements are applicable at the time that the surveillance =is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedia1' measures that apply.

However, the Surveillance Requirements have to be met to dentonstrate that inoperable equipment has been restored to OPERABLE status.

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement.

The purpose of.this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components 1

ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL CONDITIONS or other-specified conditions associated with plant shutdown as well as startup.

Under the provisions of this spe.:ification, the applicable Surveillance

.,c,

Requirements must be performed within the specified surveillance interval to assume that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation.

P RIVER BEND - UNIT 1 B 3/4 0-5 Amendment No. 47

,~

APPLICABILITY BASES S?ecification 4.0.5 establishes the requirements that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10CFR50.55a.

These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for per-forming the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda... This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of t'his specification, the more restrictive requirements of:ths Technical Specifications take precer<ence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.

The requirements of Specification 4.0.4-to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision thst allows pumps and valves to be tested up to one week af ter return to normal operation.

The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME 9 oiler and Pressure Vessel Code provision that allows a valve to be incapabia of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable, I

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RIVER BEND - UNIT 1 B 3/4 0-6 Amendment No. 47

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ML20059F383

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Attachment:

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