ML18054A638

Proposed Tech Specs,Incorporating Revs of Sections 3.0 & 4.0 of STS Re Limiting Conditions for Operation & Surveillance Requirements,As Described in Generic Ltr 87-09

ML18054A638
Person / Time
Site:	Palisades
Issue date:	04/03/1989
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18054A637	List: ML18054A636 ML18054A638 ML18054A646
References
GL-87-09, GL-87-9, NUDOCS 8904130405
Download: ML18054A638 (21)

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ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION CHANGE PAGES April 3, 1989 f----'-----------L-~

8904130405 890403 /~/,

-PDR ADOCK 05000255

-P . PDC I 11 l:,,i 19 Pages OC0588-0025-NL02-NL04

\:-

LIMITING CONDITIONS FOR OPERATION

'3.0 APPLICABILITY

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-hIMIT-ING--COND I-TION S--FOR_ OPERA'I'IQN ______ _

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3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the plant 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 and/or associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, within one hou~

• action shall be initiated to place the unit in a condition in which the Specification does not apply by placing it, as applicable, in:

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTDOWN within the. following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

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

Where corrective measures are completed that permit operation under the action requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual Specifications.

3.0.4 Entry into a reactor operating condition or other specified I condition shall not be made when the conditions for the Limiting I Conditions for Operation are not met and the associated action I requires a shutdown if they are not met within a specified time I interval. Entry into a reactor operating condition or other I specified condition may be made in accordance with action I requirements when conformance to them permits continued I operation of the facility for an unlimited period of time. I This provision shall not prevent passage through or to reactor operating conditions as required to comply with action requirements. _Exceptions to these requirements are stated in t.he individual specific-at ions.-

3-1 Amendment No. it, SJ, TSP0588-0025-NL02-NL04

3.0 BASIS

• LIMITING CONDITIONS FOR OPERATION

• I I

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Specification 3. 0.1 through 3. O. 4 establi~h_t_h_e_ generai-requfrements * - - - ------ -/------

applicable to Limiting Conditions for Operation. These requirements are I based on the requirements for Limiting Conditions for Operation stated in I the Code of Federal Regulations, 10 CFR S0.36(c)(2): I "Limiting conditions for operation are the lowest functional capability I or performance levels of equipment required for safe operation of the I facility. When a limiting condition for operation of a nuclear reactor is I not met, the licensee shall shut down the reactor or follow any remedial I action permitted by the technical specifications until the condition can /.

be met." I Specification 3.0.1 establishes the Applicability statement within each I individual specification as the requirement for when (i.e., in which */

plant condition or other specified conditions) conformance to the I Limiting Conditions for Operation is required for safe operation of the I facility. The action requirements establish those remedial measures that I must be taken within specified time limits when the requirements of a I Limiting Condition for Operation are not met. I There are two basic types of action 'requirements. The first specifies the I remedial measures that permit continued operation of the facility which is I not further restricted by the time limits of the action requirements. In I this case, conformance to the action requirements provides an acceptable I level of safety for unlimited.continued operation as long as the action I requirements continue to be met. The se.cond type of action requirement

• I specifies a time limit in which conformance to the conditions of the I Limiting Condition for Operation must be met. This time limit fs the I allowable outage time to restore an inoperable system or component to I OPERABLE status or for restoring parameters within specified limits. If /

these actions are not completed within the allowable outage time limits, a I shutdown is required to place the facility in a plant condition in which I the specification no longer applies. It is not intended that the shutdown I action requirements be used as an operational convenience which permits I (routine) voluntary removal of a system(s) or component(s) from service I in lieu of other alternatives that would not result in redundant systems I or components being inoperable. I The specified time limits of the action requirements are applicable from I the point in time it is *identified that a Limiting Condition for Operation I is not met. The time limits of the action requirements are also applicable I when a system or component is removed from service for surveillance testing I or investigation of operational problems. Individual specifications may I include a specified time limit for the completion of.a Surveillance I Requirement when equipment is removed from service. In this case, the I allowable outage time limits of the action requirements are applicable when I this time limit expires if the surveillance has not been completed. When a I shutdown is required to comply with action requirements, the plant may have I entered a plant condition in which a new specification becomes applicable. I

.In this case, the time limits of the action requirements would apply from I

. the point :in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met. I 3-la Amendment No.

TSP0588-0025-NL02-NL04

,. 3.0 BASIS (Continued)*

'LIMITING CONDITIONS FOR OPERATION

• I I

- ---- ----~- ---- --- - -

Specification 3.0. 2 establishes that noncompliance with a specfficaifon ---- - --

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exists when the requirements of the Limiting Condition for Operation are I not met and the associated action requirements have not been implemented /

within the specified time interval. The purpose of this specification is I to clarify that (1) implementation of the action requirements within the I

.to specified interval constitutes compliance with a specification and I (2) completion of the remedial measures of the action requirements is not I required when compliance with a Limiting Condition for Operation is restored I within the time interval specified in the associated action requirements. I Specification 3.0.3 establishes the shutdown action requirements that must I be implemented when a Limiting Condition for Operation is not met and the I condition is not specifically addressed by the associated action I requirements. The pµrpose of this specification is to delineate the time I limits for placing the unit in a safe shutdown condition when the plant I operation cannot be maintained within the limits for safe operation defined l by the Limiting Conditions for Operation and its action requirements. It is I not intended to be used as an.operational convenience which permits (routine) /

voluntary removal of redundant systems or components from service in lieu of I other alternatives that would not result in redundant systems or components I being inoperable. One hour is allowed to prepare for an orderly shutdown I before initiating a change in plant operation. This time permits the I operator to coordinate the reduction in electrical generation with the load I dispatcher to ensure the stability and availability of the electrical grid. I The.time limits specified to reach lower plant conditions of operation I permit the shutdown.to proceed in a controlled and orderly manner that is I well within the specified maximum cooldown rate and within the cooldown I capabilities of the facility assuming only the minimum required equipment I is operable. This reduces thermal stress on components of the primary I coolant system and the potential for a plant upset that could challenge I safety systems under conditions for which this specification applies. I If remedial measures permitting limited continued operation of the I facility under the provisions of the action requirements are completed, I the shutdown may be terminated. The time limits of the action I requirements are applicable from the point in time there was a failure I to meet a Limiting Condition for Operation. Therefore, the shutdown may I be terminated if the action requirements have been met or the time limits I of the action requirements have not expired, thus providing an allowance I for the completion of the required actions. I The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to I be in cold shutdown when a shutdown is required during power operation. I If the plant is in a lower operation condition when a shutdown is required,_ I the time limit for reaching the next lower condition of operation applies. I However, if a lower operating condition is reached in less time than I allowed, the total allowable time to reach cold shutdown, or other I 3-laa Amendment No.

TSP0588-0025-NL02-NL04

3.0 BASIS (Continued)

• LIMITING CONDITIONS FOR OPERATION

• I I

- -- app-li-c-ab-1e-condition-,--+/-s-not-reduced-. --Fol:' examp-le-,-- f--hot-standby--is _______ L ____

reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach hot shutdown is the next I 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to reach hot shutdown is not reduced from I the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Therefore, if remedial measures are I completed that would permit a return to power operation, a penalty is not I incurred by having to reach a lower plant operating condition in less I than the total time allowed. I The same principle applies with regard to the allowable outage time limits I of the actio_n requirements, if compliance with the action requirements for I one specification results in entry into a condition of operation for another I specification in which the requirements of the Limiting Condition for I Operation are not met. If the new specification becomes applicable in less I time than *specified, the difference may be added to the allowable outage I time limits of the second specification. However, the allowable outage I time limits of action requirements for a higher reactor operating condition I of operation may not be used to extend the ailowable outage time that is I applicable when a Limiting Condition for Operation. is not met in a lower I plant condition of operation. I The shutdown requirements of Specification 3.0.3 do not apply during cold I shutdown and refueling because the action requirements of individual I specifications define the remedial measures to be taken. I Specification 3.0.4 establishes limitations on reactor operating condition I changes when a Limiting Condition for Operation is not met. It precludes I placing the facility in a higher operational condition when the I requirements for a Limiting Condition for Operation are not met, and I continued noncompliance to these conditions would result in a shutdown to I comply ~ith *the action requirements if a change in plant conditions were I permitted. The purpose of this specification is to ensure that facility I operation is not initiated or that higher reactor operating conditions I are not entered when corrective action is being taken to obtain compliance I with a specification by restoring equipment to operable status or I parameters to specified limits. Compliance with action requirements that I permit continued operation of the facility for an unlimited period of I time provides an acceptable level of safety for continued operation I without regard to the status of the plant before or after a change in I plant condition. Therefore, in this case, entry into a reactor operating I condition or other specified condition may be made in accordance with I the provisions of the action requirements. The provisions of this I specification should not, however, be interpreted as endorsing the I failure to exercise good practice in restoring systems or components to I operable status before plant startup. I When a shutdown is required to comply with action requirements, the I provisions of Specification 3.0.4 do not apply because they would delay I placing the facility in a lower plant condition of operation. I 3-lab Amendment No.

TSP0588-0025-NL02-NL04

• Table 3.17.1 Instrumentation Operating Requirements for Reactor Protective System Minimum Minimum Permissible Operable Degree of Bypass

-NO. _____ Funct: fi>narunn:- --- --channe-ls -*- *-Redundancy - - - .. *-** -- .Condit ions ____________________

1. Manual (Trip 1 None None Buttons) (g) I

2. Variable High None Power Level (g) I

3. Log Range 2 1 Below 10- 4 %(e) or Above Channels (g) 15% Rated Power(a) Except I as Noted in (c)

-4 (e)

4. Thermal Margin/ 1 Belowcl9 % of Rated Low-Pressurizer Power and greater than Pressure (g) cold shutdown boron con- I centration.

5. High-Pressurizer 1 None Pressure (g) I

-4 (e)

6. Low Flow Loop (g) 1 Belowcl9 % of Rated I Power and greater than cold shutdown boron con-centration.

7. Loss of Load (h) 1 None None I

8. Low Steam Gen- l/Steam None erator Water Generator Level (g) I

• -4 (e)

9. Low Steam Gen- l/Steam Below(19 % of Rated era,tor Pressure Generator Power a and greater than (g) cold shutdown boron con- I centration.

10. High Containment 2(b) 1 None Pressure (g) I (a) Bypass automatically removed.

(b) One of the inoperable channels must be in the tripped condition.

(c) Two channels required if TM/LP, low steam generator or low-flow channels are bypassed.

(d) If only two channels are operable, load shall be reduced to 70% or less

• of rated power. - _ -1 4

(e) For low power physics testing, 10 % may be increased to 10 % and cold shutdown boron concentration is not required.

(f) Axial Offset operability requirements are given in Specification 3.11. 2. I (g) Required operable if any clutch power supply is energized. I (h) Automatically bypassed below 15% power. I 3-78 Amendment No. 11$,

TSP0588-0025-NL02-NL04

4.0 SURVEILLANCE REQUIREMENTS

• 4.0.1 Surveillance requirements shall be applicable during the reactor

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op*erating conditions-associated-with~individuaL.Limiting __________

Conditions for Operation unless otherwise stated in an individual surveillance requirement.

4.0.2 Unless otherwise specified, each surveillance requirement shall

.be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25% of the surveillance interval, and

b. A total maximum combined interval time for any three consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement withtn the allowed I surveillance interval, defined by Specification 4.0.2, shall I constitute noncompliance with the operability requirements for a I Limiting Condition for Operation. The time limits of the action I requirements are applicable at the time it is identified that a l Surveillance Requirement has not been performed. The action I requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the I completion of the surveillance when the allowable outage time I limits of the action requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I Surveillance Requirements do not have to be performed on I inoperable equipment. I 4.0.4 Entry into a reactor operating condition or other specified I condition shall not be made unless the Surveillance Requirement(s) I associated with a Limiting Condition of Operation has been I performed within the stated surveillance int.erval or as otherwise I specified. This provision shall not prevent passage through or I to plant conditions as required to comply with action requirements. I 4.0.5 Surveillance Requirements for inservice inspection and testing I of ASME Code Class 1, 2, and 3 components shall be applicable I as follows: I

a. Inservice inspection of ASME Code Class 1, 2, and 3 I components and inservice testing of ASME Code Class 1, 2, I and 3 pumps and valves shall be performed in accordance. I with Section XI of the ASME Boiler and Pressure Vessel I Code and applicable Addenda as required by 10 CFR 50, I Section 50.55a(g), except where specific written relief I has been granted by the Conunission pursuant to 10 CFR 50, I Secti6~ 50.55a(g)(6)(i). I 4-1 Amendment No. Z~,

TSP0588~0025-NL02-NL04

'4. 0 SURVEILLANCE REQUIREMENT (Continued)

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b. Surveillance intervals specified in- Section-XI. ofthe-ASME----*--- --/---~-

Boiler and Pressure Vessel Code and applicable Addenda for the I inservice inspection and testing activities required by the I ASME Boiler and Pressure Vessel Code and applicable Addenda I sha'll be applicable as follows in these Technical I Specifications: I ASME Boiler and Pressure Vessel Required frequencies I Code and applicable Addenda for performing inservice I terminology for inservice inspection and testing I inspection and testing activities activities I Weekly. At least once per 7 days I Monthly At least once per 31 days I Quarterly or every 3 months At least once per 92 days I S~miannually or every 6 months At least once per 184 days I Every 9 months At least once per 276 days I Yearly or annually At least once per 366 days I

c. The provisions of Specification 4.0.2 are applicable to the I above required frequencies for performing inservice inspection I and tes~ing activities. I

d. Performance of the above inservice inspection and testing I activities shall be in addition to other specified I Surveillance Requirements. I

e. Nothing in the ASME Boiler and Pressure Vessel Code shall I be construed to supersede the requirements of any Technical I Specification. I

.4-la Amendment No.

TSP0588-0025-NL02-NL04

• ' 4.0 BASIS * *

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*Speci-fi-cat-ions- -4 .-0-.-1--through_.£..*.O.* S..es_t~bJ,i__~_h __t_!i~ g_~neral requirements I applicable to Surveillance Requirements. These requirements- are--basea -on*-*---------;-------

the Surveillance requirements stated in the code of Federal Regulations, I 10 CFR 50.36(c)(3): . /

"Surveillance requirements are requirements relating to test, I calibration, or inspection to ensure that the necessary quality I of systems and components is maintained, that facility operation I will be within safety limits, and that the limiting conditions I of operation will be met." I Specification 4. 0.1 establishes the requirement. that surveillances must be I performed during reactor operating conditions or other conditions for which I the requirements of the Limiting Conditions for Operation apply, unless I otherwise stated in an individual Surveillance Requirement. The purpose I of this specification is to ensure that surveillances are performed to I verify the operational status of systems and components and that parameters r are within specified limits to ensure safe operation of the facility when I the plant is in a reactor operating condition or other specified condition I for which the associated Limiting Conditions for Operation are applicable. I Surveillance Requirements- do not have to be performed when the facility I is in an operational condition for which the requirements of the associated I Limiting Condition for Operation do not apply, unless otherwise specified. I The Surveillance Requirements associated with a Special Test Exception I are only applicable when the Special Test Exception is used as an allowable I exception the the req~irements of a specification.* I Specification 4.0.2 establishes the conditions under which the specified I time interval for Surveillance Requirements may be extended. Item a. I permits *an allowable extension of the normal surveillance interval to I facilitate surveillance scheduling and consideration of plant operating I conditions that may not be*suitable for conducting the surveillance; I e.g., transient conditions or *other ongoing surveillance or maintenance I activities. Item b. limits the use of the provisions of item a. to ensure I that it is not used repeatedly to extend the surveillance interval beyond I that specified. The limits of Specification 4.0.2 are based on engineering I judgment and the recognition that the most probable result of any particular I surveillance being performed is the verification of conformance with the I Surveillance Requirements. These provisions are sufficient to ensure that I the reliability ensured through surveillance activities is not I significantly degraded beyond that obtained from the specified .surveillance I interval*. I Specification 4.0.3 establishes the failure to perform a Surveillance I Requirement within the allowed surveillance interval, defined by the I provisions of Specification 4.0.2, as a condition that constitutes a I failure to meet the operability requirements for a Limiting Condition I for Operation. Under the provisions of this specification, systems and I components are assumed *to be operable when Surveillance Requirements have I 4-lb Amendment No.

TSP0588-0025-NL02-NL04

4.0 BASIS (Continued)* /

• I I

been-satisfactor1Ty-pe_r_formed --within- the-spec-Hied- -t-ime-interv.al_. __ RQ_w~y_~_!'.:_!__ I nothing in this provision is to be construed as implying that systems or ------7-----

components are operable when they are found or known to be inoperable I although still_ meeting the Surveillance Requirements. This specification I also clarifies that the action requirements are applicable when I Surveillance Requirements have not been completed within the allowed I surveillance interval and that the time limits of the action requirements I apply from the point in time it is.identified that a surveillance interval I was exceeded. Completion of the Surveillance Requirement within the I allowable outage time limits of the action requirements restores compliance I with the requirements of Specifica~ion 4.0.3. However, this does not I negate the fact that the failure to have performed the surveillance I within the allowed surveillance interval, defined by the provisions of I Specification 4.0.2, was a violation of the operability requirements of I a Limiting Condition for Operation that is subject to enforcement action. I Further, the failure to perform a surveillance within the provisions of I Specifications 4.0.2 is a violation of a Technical Specification I requirement and is, . therefore, a reportable event .under the requirements I of 10 CFR 50.73(a)(2)(i)(B) because it is a condition prohibited by the I plant's Technical Specifications. I If the allowable outage time limits of the action requirements are less I than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with action requirements, I e.g., Specification 3.0.3, a 24-hour allowance is provided to pennit a I delay in implementing action requirements. This provides an adequate time *I limit to complete Surveillance Requirements that have not been performed. I The purpose of this allowance *is* to p"ermit the completion of a surveillance I before a shutdown is required to comply with action requirements or before I other remedial ~easures would be required that may preclude completion of I a surveillance. The basis for this allowance includes consideration for I plant conditions, adequate planning, availability of personnel, the time I required to perform the surveillance, and the safety significance of the I delay in completing the required surveillance. This provision also I provides a time limit for the completion of Surveillance Requirements that I become applicable as a consequence of plant condition changes imposed by I action requirements and for completing Surveillance Requirements that are I applicable when an exception to the requirements of Specification 4.0.4 is I allowed. If a surveillance is not completed within the 24-hour allowance, I the time limits of the action requirements are applicable at that time. I When a surveillance is performed within the 24-hour allowance and the I Surveillance Requirements are not met, the time limits of the action I requirements are applicable at the time that the surveillance is I terminated. I Surveillance Requirements do not have to be performed*on inoperable I equipment because the action requirements define the remedial measures I that apply. However, following expiration of the surveillance interval, I the Surveillance Requirements have to be met to demonstrate that I inoperable equipment has been restored to OPERABLE status. I 4-lc Amendment No.

TSP0588-0025-NL02-NL04

4.0 BASIS (Continued) *

• I I

Spe-cif+/-cation- 4-.-0-.4- est-abl-ishes--the_ r_equit_eme_u._t__ J;l}a_t;_ ~_1_1_ applicable I

surveillances must be met before entry into a reactor operati:ng-c-onditT6n- ------ - --r--- ----- -

or other condition of operation specified in the Applicability statement. I The purpose of this specification is to ensure that system and component I operability requirements or parameter limits are met before entry into an I operational condition for which these systems and components ensure safe I operation of the facility. This provision applies to changes in reactor I operating conditions or other specified conditions associated with plant I shutdown as well as startup. I Under the provisions of this specification, the applicable Surveillance I Requirements must be perforined within the surveillance interval to ensure I that the Limiting Conditions for Operation are met during initial plant I startup or following a*plant outage. I When a shutdown is required to comply with action requirements, the I provisions of Specification 4.0.4 do not apply because this would delay I placing the facility in a lower operational condition. I Specification 4.0.5 establishes the requirement that inservice inspection I of ASME Code Class 1, 2, and 3 components and inservice testing of ASME I Code Class 1, 2, and 3 pumps and valves shall be performed in accordance I with a periodically updated version of Section XI of the ASME Boiler and I

__ Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These I requirements apply, except when relief has been provided in writing by I the Commission. I This specification includes clarification of the frequencies for I performing the inservice inspection and testing activities required by I Section_ XI of the ASME Boiler and Pressure Vessel Code and applicabie I Addenda. This clarification is provided to ensure consistency in I surveillance intervals throughout the Technical Specifications and to I remove ambiguities relative to the frequencies for performing the I required inservice inspection and testing activities. I Under the terms of this specification, the more restrictive requirements I of the Technical Specifications take precedence over the ASME Boiler and I Pressure Vessel Code and applicable Addenda. The requirements of I Specification 4.0.4 to perform surveillance activities before entry into I a reactor operating condition or other specified condition takes precedence I over the ASME Boiler and Pressure Vessel Code provision which allows pumps I and valves to be tested up to one week after return to normal operation. I The Technical Specification definition o~ operable does not allow a grace I period before a component, that is not capable of performing its specified I function, i-s declared inoperable and takes precedence over the ASME_Boiler /

and Pressure Vessel Code provision which allows a valve to be incapable of I performing its specified function for up. to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared I inoperable. I 4-ld Amendment No.

TSP0588-0025-NL02-NL04

4. 1

• INSTRUMENTATION AND CONTROL Applicability

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---Appl-ies-t-o--t-he-reactor__ prote_~tiy_e___~y~tem and other critical

. instrumentation and controls. ----------------------------------------------

Objective To specify the minimum frequency and type of surveillance to be applied to critical plant instrumentation and controls.

Specifications Calibration, testing, and checking of instrument channels, reactor protective system and engineered safeguards system logic channels and miscellaneous instrument systems and controls shall be performed as specified in 4.1.1 and in Tables 4.1.1 to 4.1.3.

4.1.1 Overpressure Protection Systems

a. Each PROV shall be demonstrated operable by:

1. Performance of a channel functional test on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required operable and at least once per 31 days thereafter when the PORV is required operable"

2. Performance of a-channel calibration on the PORV actuation channel at least once per 18 months.

3. Verifying the PORV isolation valve is open at* least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure protection.

4. Testing in accordance with the inservice inspection requirements for ASME Section XI, Section IWV Category C valves.

4-le Amendment No. $1, TSP0588-0025-NL02-NL04

TABLE 4.1.1 (.

Minimum Frequencies- for Checks, Calibrations and Testing of Reactor Protective System(S)

Surveillance Channel Description Function Frequency Surveillance Method

1. Power Range Safety Channels a. Check (7) s a. Comparison of four-power channel readings. I

b. Check(3) D b. Channel adjustment to agree with heat balance calculation. Repeat whenever flux-~T power comparators alarms.

c. Test M(2) c. Internal test signal.

2. Wide-Range Logarf~hmic Neutron Monitors

• d.

a.

b.

Calibrate (6)

Check Test R

s p

d.

a.

b.

Channel alignment through measurement/adjustment of internal test points.

Comparison of both wide-range readings.

Internal test signal.

3. Reactor Coolant Flow a. Check s a. Comparison of four separate total flow indications

b. Calibrate R b. Known differential pressure applied to sensors.

c. Test M(2) c. Bistable trip tester.(1)(4)

4. Thermal Margin/Low a. Check: (8) s a. Check: I Pressurizer Pressure (1) Temperature (1) Comparison of four separate calculated Input trip pressure set point indications.

(2) Pressure (2) Comparison of four pressurizer pressure Input indications. Same as S(a) below.)

b.

c.

Calibrate (1) Temperature Input (2) Pressure Test Input R

H(2) b.

c.

Calibrate:

(1) Known resistance substituted for RID coinci-dent with known pressure and power input.

(2) Part of S(b) below.

Bistable trip tester.(1)

s. High-Pressurizer Pressure a. Check (8) - s a. Comparison of four separate pressure indications. i I

b. Calibrate R b. Kne>Wn pressure applied to sensors. I

c. Test H(2) c. Bistable trip tester.(1)

I i

4-3 Amendment No. J~, tt~,

TSP1088-0181-NL04-NL02

TABLE 4.1.1 Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System(S) (Contd)

Surveillance Channel Description Function Frequency Surveillance Method

6. Steam Generator Level a. Check s a. Comparison o.f four level indications per ge.nerator.

b. Calibrate R b. Known differential pressure applied to sensors.

• 7. Steam Generator Pressure c.

a.

b.

c.

Test Check Calibrate Test M(2) s R

M(2) c.

a.

c.

Bistable trip tester.(l)

Comparisons of four pressure indications per generator.

Known pressure applied to sensors.

Bistable trip tester.(l)

8. Containment Pressure a. Calibrate R a. Known pressure applied to sensors.

b. Test M(2) b. Simulate pressure switch action.

9. Loss of Load a. Test p a. Manually trip turbine auto stop oil relays.

10. Manual Trips a. Test p a. Manually test both circuits.

11. Reactor Protectfon System Logic Units

12. Axial Shape Index (ASI) a.

a.

Test Test M(2)

R a.

a.

Internal test circuits.

Known power inputs applied to Thermal Margin Calculator.

13. 6T Power a. Check (7) s a. Same as l(a). I

b. Check (3) D b. Same as l(b).

c. Test R c. Known temperature imputs applied to Thermal Margin Calculator.

i 4-4 Amendment No $'1, "' tts/,

TSP1088-0181-NL04-NL02

• TABLE 4.1.1

• M~ni.mum Frequencies for Checks, Calibrations and Testing of Reactor Protective System(5) (Contd)

Surveillance Channel Description Function Frequency Surveillance Method

14. Thermal Margin Calculator a. Check Q a. Verify constants.

NOTES: (l)The bistable trip tester injects a signal into the bistable and provides a precision readout of the trip set pointf (2)All monthly tests will be done on only one of four channels at a time to prevent reactor trip.

(3)Adjust the nuclear power or power.

~T power until rea~out agrees with heat balance calculations when above 15\ of rated (4)Trip setting for op~rating pump combination only. Settings for other than operating pump combinations must_ be tested during routine monthly testing performed when shut. down and within four hours after resuming operation with a different pump combination if the s~tting for that combination has not been tested within the previous month. j I

(5)It is not necessary to perform the specified testing during prolonged periods in the refueling shutdown condition:

i If this occurs, omitted testing will be performed prior to returning the plant to service. 1 (6)Also includes testing variable high power function in the Thermal Margin Calculator.

(7)Required if the reactor is critical. I (8)Required when PCS is > 1500 psia. I FREgUENCY NOTATION Notation s

D w

Frequency At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 6 months.

R At least once per 18 months.

p Prior to each start-up if not done

)

previous week.

NA Not applicable.

4-5 j Amendment No $~, t:tS, TSP1088-0181-NL04-NL02 II

I r ..

r .

TABLE 4.1. 2 I I

I I ,-

Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls Surveillance Channel Description Function Frequency Surveillance Method

1. Low-Pressure SIS Initiation Channels a.

b.

c.

Check Test(l)

Test S(4)

R M(2) a.

b.

c.

Comparison of four separate pressure indications.

Signal to meter relay adjust with test device to verify SIS actuation logic.

Signal to meter relay adjusted with test device.

I I *

2. Low-Pressure SIS Signal Block a. Test(l) R a *. *Part of l(b) above. I Permissive and Auto Reset

3. SIS Actuation Relays a. Test Q a. Simulation of SIS 2/4 logic trip using built-in testing system. Both "standby power" and "no standby power" circuits will be tested for left and right channels. Test will verify functioning of initiation circuits of all equipment normally operated by SIS signals.

b. Test R b. Complete automatic test initiated by same method as Item l(b) and including all normal automatic operations.

4. Containment High-Pressure a. Calibrate R a. Known pressure applied to sensors.

Channels

b. Test R b. *Simulation of CHP 2/4 logic trip to verify actuation logic for SIS, containment isolation and containment spray.

c. Test M(2) c. Pressure switch operation simulated by opening or shorting terminals or pressure applied to the switch.

5. Containment High Radiation a. Check D a. Comparison of four separated radiation level Channels indications.

b. Calibrate R b. Exposure to known external radiation source.

4-6 Amendment No $~, --'

TSP0289-0025-NL04

I 1

TABLE. 4. 1. 2 I

Minimum Frequencies for Checks, Calibrations and Testing of I Engineered Safety Feature Instnunentation Controls (Contd)

Surveillance Channel Description Function* Frequency Surveillance Method

s. Containment High Radiation c. Test M(2) c. Electronic circuit check of signal amplifier Channels (Contd) to verify proper indicator operation.

d. Test R d. Simulation of CHR 2/4 logic trip with test switch to verify actuation relays, including containment isolation.

6. Manual SIS Initiation a. Test R a. Manual push-button test.

7. Manual containment a. Test R a. Manual push-button test.

Isolation Initiation

b. Check R b. Observe isolation valves closure.

8. Manual Initiation Containment a. Test R a. Manual switch operation.

Spray Pumps and Valves . I' 9 DBA Sequencers a. Test Q a. Proper operation will be verified during SIS actuation test of Item 3(a) above.

10. Normal Shutdown Sequencers a. Test R a. Simulate normal actuation with test-operate switch and verify equipment starting circuits.

11. Diesel Start a. Test M a .* Manual initiation followed by synchronizing and loading.

b. Test R b. Diesel start, load shed, synchronizing and loading will be verified during Item 3(b) above.

c. Test p c. Diesel auto start initiating circuits.

12. SIRW Tank Level Switch a. Test R a. Level switches removed from fluid to verify Interlocks a.ctuation logic.

4-7 Amendment No. $~, ~4, TSP0289-0025-NL04

Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls (Contd)

Surveillance Channel Description Function Frequency Surveillance Method 13.

14.

Safety Injection Tank Level and Pressure Instruments Boric Acid Tank Level Switches a.

b.

a.

Check Calibrate Test s

R R

a.

b.

a.

Verify that level and pressure indication is between independent high high/low alarms for level and pressure.

Known pressure and differential pressure applied to pressure and level sensors.

Pump tank below low-level alarm point to I

I I

I I

verify switch operation.

I

15. Boric Acid Heat Tracing System a~ Check D a. Observe temperature recorders for proper readings.

16, Main Steam Isolation Valve a. Check s a. Compare four independent pressure* indications.

Circuits

b. Test(3) R b. Signal to meter relay adjusted with test device to verify HSIV circuit logic.

17. SIRW Tank Temperature a. Check M a. Compare independent temperature readouts.

Indication and Alarms b. Calibrate R b. Known resistance applied to indicating loop.

18. Low-Pressure Safety Injection a. Check p a. Observe valve is open with air supply isolated.

Flow Control Valve CV-3006

19. Safety Injection Bottle a. Check p a. Ensure each valve open by observing valve Isolation Valves position indication and valve itself. Then lock open breakers and control power key switches.

20. Safety Injection Miniflow a. Check p a. Verify valves open and HS-3027 and 3056 positioned Valves CV-3027', 3056 to maintain them open.

NOTES: (l)Calibration of the sensors is performed during calibration of Item 5(b), Table 4.1.1.

(2)All monthly tests will be done on only one channel at a time to prevent protection system actuation.

(3)Calibration of the sensors is performed during calibration of Item 7(b), Table 4.1.1.

(4)Required when PCS is > 1500 psia. I 4-8 Amendment No. $~, ' ' ' t~t, TSP0289-0025-NL04

II J *-.

f 1*  :.

I I

TABLE 4.1.2 I

I Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls (Continued)

I I I I

I I

I I

FREqtJENCY NOTATION I

Notation Freguencl'.:

s At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 1.

w At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 6 months.

R At least once per 18 months.

p Prior to each start-up i f not done previous week.

NA .Not applicable.

4-9 Amendment No. 1~,

TSP0289-0025-NL04

---~*-:-,---,,~--

4.3 SYSTEMS SURVEILLANCE

--AP-P-LICABILITX ___ _

Applies to preoperational and inservice structural surve-:f.Ilance ___ ---- ----- -.

of the reactor vessel and other Class 1, Class 2 and Class 3 system components.

OBJECTIVE To insure the integrity of the Class 1, Class 2 and Class 3 piping systems and components.

SPECIFICATIONS a,b,c,d - ~eleted I

e. The Inservice Inspection program shall be reevaluated as required by 10 CFR 50, Section 50.55a(g)(5) to consider incorporation of new inspection techniques that have been proven practical~ and the conclusions of the evaluaiion shall be used as appropriate to update the inspection program.

f. Surveillance of the regenerative heat exchanger and primary coolant pump .flywheels shall be performed as indicated in Table 4.3.2.

• g. A surveillance program to monitor radiation induced changes in the mechanical and impact properties of the reactor vessel materials shall be maintained as described in Section 4.5.3 of the FSAR. The specimen removal schedule shall be -as indicated in Table 4.3.3.

4-16 Amendment No. ii, TSP0588-0025-NL02-NL04

--.-*-**-* _\)

]._

,,f

..:*i. " SYSTEMS SURVEILLANCE

. _________h-.---Periodic__

• l~~-~.!!ge (Continued) testing (a), (b) on each check valve listed I

in Table 4. 3. 1 shall-De-accompltshed -prioi:-to-returning to the Power Operation Condition after every time- the plant ~has_________ -- -

been placed in the Refueling Shutdown Condition, or the Cold Shutdown Condition for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if such testing has not been accomplished within the previous 9 months, and prior to returning the check valves to service after maintenance, repair or replacement work is performed on the valves.

i. Whenever integrity of a pressure isolation valve listed in I Table 4.3.1 cannot be demonstrated and credit is being taken for compliance with Specification 3.3.3.b, the integrity of the remaining check valve in each high pressure line having a leaking valve shall be determined and recorded daily and the position of the other closed valve located in that pressure line shall be recorded daily.

j. Following each use of the LPSI system for shutdown cooling, the reactor shall not be made critical until the LPSI check valves (CK-3103, CK-3118, CK-3133*and CK-3148) have been verified closed.

I (a)

To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if supported by computations showing that the method is capable of demonstrating valve

• compliance with- the leakage criteria *.

(b)Reduced pressure testing is acceptable (see footnote 5 to Table 4.3.1).

Minimum test differential pressure shall not be less than 150 psid.

4-17 Amendment No 7t lJY, hAeidedl¥11~tdetl~atid t;tt1/t0J/t9St/l~liltY.

TSP0588-0025-NL02-NL04