ML20012E863

Amend 130 to License DPR-20,changing Tech Sepcs to Incorporate Revised Sections 3.0 & 4.0 of STS Re Limiting Conditions for Operation & Surveillance Requirements,Per Generic Ltr 87-09

ML20012E863
Person / Time
Site:	Palisades
Issue date:	03/23/1990
From:	Thoma J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20012E864	List: ML20012E863 ML20012E866
References
GL-87-09, GL-87-9, NUDOCS 9004060468
Download: ML20012E863 (23)

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UNITED STATES I

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LONSUMERSPOWERCOMPANY PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE i-Amendment No.130 t

License No.. DPR-20 1.

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

A.

The application for amendment by Consumers Power Company (the i

licensee) dated April 3,1989, con; plies with the standards and requirements of the Atomic Energy Act of 1954, as arended (the Act), and the Commission's rules and regulations set forth in i

10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorizec I

by this amendment can be cor:fucted without endangering the health arid safety of the public; and (ii) that such activities will be ccnducted in compliance with the Corcission's regulations; D.

The issuance of this amendment will net be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requiren.ents have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license i

ar.iendment and Paragraph 3.B. of Provisional Operating License No. DPR-20 is hereby amended to read as follows:

i Technical Specifications i

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.130, are hereby incorporated in the license. The licensee shall operate the facility i

in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented not later than May 7, 1990.

FOR THE NUCLEAR REGULATORY COMMISSION 4

0W J hn 0. Thema Acting Director Project Directorate 111-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation Attachmcnt:

Cher.ges to the Technical Spcifications Date of Issuance: March 23,1990 L

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ATTACHMENT TO LICENSE AltENDMENT fl0. 130

?Qy}QQLQffkT)ff,}},Cfy}{,N0_.DPR-20 DOCKET NO. 50-255 Pevise Appendix A Technical Specifications by removing the pages identified t'elew and inserting the attached pages. The revised pages are identified by the captiened amendment number and contain marginal lines indicating the area of change. REMOVE INSERT 3-1 3-1 3-la 3-laa 3-lab 3-78 3-78 4-1 41 4-la 4-lb 4-Ic 4-Id 4-le 4-3 4-3 4-4 4-4 4-5 4-5 4-6 4-6 4-8 ' 4-8 4-9 4-9 4-16 4-16 d-17 4-17 d-18 4-18 l l l l l l l l l l l l l l l

y 0 'LI$ZTING CONDIT80NS FOR OPERATION a 3.0 APPLICABILITY LIMITING CONDITIONS FOR OPERATION 3.0.1 compliance with the Limiting conditions for operation contained in L 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 k' hen 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 hour 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 hours, 2. At least HOT SHUTD0k'N within the following 6 hours, and 3. At least COLD SHUTD0k'N within the subsequent 24 hours. k'here 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 / Conditions for Operation are not met and the associated action / requires a shutdown if they are not met within a specified time / interval. Entry into a reactor operating condition or other / specified condition may be made in accordance with 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 reactor i operating conditions as required to comply with action requirements. Exceptions to these requirements are stated in l the individual specifications. 3-1 Amendment No. 31, 85, 130

,, 3.0 BAS 8S / LIMITING CONDITIONS FOR OPERATION / Specification 3.0.1 through 3.0.4 establish the general requirements / l i 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,10 CFR 50.36(c)(2): / "Limitina. conditions for operation are the lowest functional capability / or performance levels of equipment required for safe operation of the / l 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 specifications 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 / plant condition 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 met. / There are two basic types of action requirements. The first specifies the / remedial measures that permit continued' operation of the facility which is / further restricted by the time limits of the action requirements. In / not 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 / allevable outage time to restore an inoperable system or component to / OPERABLE status or for restoring parameters within specified limits. If / these actions are not completed within the allowable outage time limits, a / shutdown is required to place the facility in a plant condition in which / the specification no longer applies. 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. / 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 a specified time limit for the completion of a Surveillance / Requirement when equipment is removed from service. In this case, the / allevable outage time limits of the action requirements are applicable when / this time limit expires if the surveillance has not been completed. When a / shutdown is required to comply with action requirements, the plant may have / entered a plant condition in which a new specification beco=es applicable. / In this case, the time limits of the action requirements would apply from / the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met. / 3-la Amenenent No.130 l

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,30 BASIS (C

ntinued)

/ ] 1 LIMITING CONDITIONS FOR OPERATION / 1 Specification 3.0.2 establishes that noncompliance with a specification / 1 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 / to clarify that (1) implementation of the action requirements within the / to specified interval constitutes compliance with a specification and / (2) completion of the remedial measures of the action requirements is not / 1 required when compliance with a Limiting Condition for Operation is restored / within the time interval specified in the associated action requirements. / Specification 3.0.3 establishes the shutdown action requirements that must / be implemented when a Limiting Condition for Operation is not met and the / condition is not specifically addressed by the associated action / requirements. The purpose of this specification is to delineate the time / limits for placing the unit in a safe shutdown condition when the plant / operation cannot be maintained within the limits for safe operation defined / by the limiting Conditions for Operation and its action requirements. It is / not intended to be used as an operational convenience which permits (routi:.e) / ' voluntary removal 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 for an orderly shutdown / before initiating a change in plant operation. This time permits the / operator to coordinate the reduction in electrical generation with the load / dispatcher to ensure the stability and availability of the electrical grid. / The time limits specified to reach lower plant 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 stress 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 ter=inated if the action requirements 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 hours for the plant to / be in cold shutdown when a shu:down is required during power operation. / If the plant is in a lower operation condition when a shutdown is required. / the time limit for reaching the next lower condition of operation applies. / However, if a lower operating condition is reached in less time than / allowed, the total allowable time to reach cold shutdown, or other / 3-laa Amendment No. 130

I Il l H I 3.,0 BASIS (Continued) / LIMITING C0h*DITIONS FOR OPERATION / applicable condition, is not reduced. For example, if hot standby is / reached in 2 hours, the time allowed to reach hot shutdown is the next / 11 hours because the total time to reach hot shutdown is not reduced from / the allevable limit of 13 hours. Therefore, if remedial secoures are / completed that would permit a return to power operation, a penalty is not / incurred by having to reach a lower plant operating condition in less / than the total time allowed. / 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 a 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 specification. However, the allowable outage / time limits of action requirements for a higher reactor operating 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 / plant condition of operation. / The shutdown requirements of Specification 3.0.3 do not apply during cold / shutdown and refueling because the action requirements of individual / specifications define the remedial measures to be taken. / I 3-lab Amendment No. 130

p Tcble 3.17.1 [ 1,. Instru'entatirn Operating Requirvents for Reacter Protective Syste7 Minimum Minimum Permissible Operable Degree of Bypass [ No. Punctional Unit Channels Redundanev Conditions 1. Manual (Trip 1 None None [ Buttons) (g) / 2. -Variable High 2(b.d) 3(d) p g Power Level (g) / Below 10% ') or Above' I 3. ' Log Range 2 1 Channels (g) 15% Rated Power (a) Except / as Noted in (c) 4. Thermal Margin / 2(b.f) 1 Belov jg % '} of Rated I g Low-Pressurizer Power and greater than Pressure (g) cold shutdown boron con- /~ centration. { 5. High-Pressuriter 2(b) 1 None Pressure (g) 6, Low Flow Loop (g) 2(b) I Belov jg %

• c' Rated

/ 1 g Power and greater than cold shutdown boron con-centration. 7 Loss of Load (h) 1 None None / 8. Low Steam Gen-2/S 1/ Steam None Gen { gym erator Water Generator Level (g) / 2/S 1/ Steam Below %(* of Rated Gen { gym Power (jg'ndgreaterthan 9. Low Steam Gen- ~ erator Pressure Generator a (g) cold shutdown boron con- / centration. 10. High Containment 2 'b) / 1 None Pressure (g) / (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. I l (d) If only two channels are operable, load shall be reduced to 70% or less of rated power. (e) For low power physics testing, 10

• may be increased to 10'I% and cold l

r!.4tdown boron concentration is not required. -(f) Axial Offset operability requirements are given in Specification 3.11.2. / 3 l (g) Required operable if any clutch power supply is energized. / (h) Automatically bypassed below 15" power. / 1 3-78 Amendment No. 118,130 1. l l r 1

p E c L F , '4. 0 SURVEILLANCE REOUIREMENTS 4.0.1 Surveillance requirements shall be applicable during the reactor operating conditions associcted with individual Limiting Conditions for Operation unless otherwise stated lJ an individual surveillance requirement., 4.0.2 Unless otherwise specified, each surveillance requirement shall be performed within the specified time interval with j 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 within the allowed / surveillance interval, defined by Specification 4.0.2, shall / constitute noncompliance with the operability requirements for a / Limiting Condition for Operation. The time limits of the action / requirements are applicable at the time it is identified that a / Surveillance Requirement has not been performed. The action / requirements may be delayed for up to 24 hours to permit the / completion of the surveillance when the allowable outage time / limits of the action requirements are less than 24 hours. / Surveillance Requirements do not have to be performed on / inoperable equipment. /. s 4.0.4 Entry into a reactor operating condition or other specified / condition shall not be made unless the Surveillance Requirement (s) / associated with a Limiting Condition of Operation has been / performed within the stated surveillanen interval or as otherwise / specified. This provision shall not prevent passage through or / to plant conditions as required to comply with action requirements. / 4.0.5 Surveillance Requirements for inservice inspection and testing / of ASME Code Class 1, 2, and 3 components shall be applicable / as follows: / Inservice inspection of ASME Code Class 1, 2, and 3 / a. components and inservice testing of ASME Code Class 1, 2 / and 3 pumps and valves shall be performed in accordance / with Section XI of the ASME Boiler 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)(6)(1). / 4-1 Amendment No. 30,51,130

0 4.0 SI'RVEII.I.ANCE REOUIREMENT (Continued) L, '} b. Surveillance intervals specified in Section XI of the ASME / Boiler and Pressure Vessel Code and applicable Addenda for the / i inservice inspection and testing activities required by the / ASME Boiler and Pressure Vessel Code and applicable Addenda / shall be applicable as follows in these Technical / Specifications / i t ASME Boiler and Pressure Vessel Required frequencies / Code and applicable Addenda for performing inservice / . terminology for inservice inspection and testing / inspection and testing activities , activities / k'eekly. At least once per 7 days / ^ Monthly At least onco per 31 days / i Quarterly or every 3 months At least once per 92 days / Semiannually or every 6 months At least once per 184 days' / Every 9 months At least once per 276 days / Yearly or annually At least once per 366 days / The provisions of Specification 4.0.2 are applicable to the / c. above required frequencies for performing inservice inspection / and testing activities. / d. Performance of the above inservice inspection and testing / activities shall be in addition to other specified / i Surveillance Requirements. / Nothing in the ASME Boiler and Pressure Vessel Code shall / e. be construed to supersede the requirements of any Technical / i Specification. / l 1 V l 4-la Amendment No. 130 l

r ,,40 BASISi i i Specificat' ions 4.0.1 through 4.0.5 establish the general requirements / applicable to Surveillance Requirements. These requirements are based on / the Surveillance-requirements stated in the code of Federal Regulations. 10 CTR 50.36(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 / vill be within safety limits, and that the limiting conditions / of operation vill be met." / Spectitcation 4.0.1 establishes the requirement that surveillances must be / [ performed during reactor operating conditions or other conditions for which / the requirements of the Limiting Conditions for Operation apply, unless / otherwise stated in an individual Surveillance Requirement. The purpose / of this specification is to ensure that surveillances are performed to / verify the operational status of systems and components and that parameters / t are within specified limits to ensure safe operation of the facility when / the plant is in a reactor operating condition or other specified condition / for which the associated Limiting Conditions for Operation are applicable. / Surveillance Requirements 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 associated with a Special Test Exception / t are only applicable when the Special Test Exception is used as an allowable / exception the the requirements of a specification. / Specification 4.0.2 establishes the conditions under which the specified / time interval for Surveillance Requirements may be extended. Item a. / permits an allevable extension of the normal surveillance interval to / f acilitate surveillance scheduling and consideration of plant operating / conditions that may not be suitable for conducting the surveillaneet / 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 / iudement and the recognition that the most probable result of any particular / " surveillance being performed is the verification of conformance with the / Surveillance Requirements. These provisions are sufficient to ensure that / the reliability ensured through surveillance activities is not / significantly degraded beyond that obtained from the specified surveillance / interval. Specification 4.0.3 establishes the f ailure to perform a Surveillance / Requirement 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 / coeponents are assumed to be operable when Surveillance Requirements have / 4 lb Amendment No. 130 l 1

esa i[ 1 1 l ', 4.0' BASIS (C:ntisted) / c L / i been satisfactorily performed within the specified time interval. However, / l nothing in this provision is 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 the allowed / surveillance interval and that the time limits of the action requirements / i apply from the point in time it is identified that a surveillance has not / been perfortaed and not at the time that the allowed serveillance interval / i 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 / i Specification 4.0.2, was a violation of the operability requirements of / a Limiting Condition for Operation that is subject to enforcement action. / Further, the failure to perform a surveillance within the provisions of / Specifications 4.0.2 is a violation of a Technical Specification / t requirement and is, therefore, a reportable event under the requirements / r of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the / plant's Technical Specifications. / i i If the allowable outage time limits of the action requirements are less / LLan 24 hours 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.in implementing 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 is required to comply with action requirements or before / other remedial measures would be required that may preclude completion of / a surveillance. The basis for this allowance includes consideration for / plant conditions, adequate planning, availability of personnel, the time / required to 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 plant 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 / Surveillance Requirements are not met,.ne time limits of the action / 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 remedial measures / i that apply. However, following expiration of the surveillance interval, / the Surveillance Requirements have to be met to demonstrate that / inoperable equipment has been restored to operable status. / Amendment No.130 o C.

1,. 0 BASIS (Crntinued) / ) Specification 4.0.4 establishes the requirement that all applicable / surveillances must be met before entry into a reactor operating condition / or other condition of operation specified in the Applicability statement. / The purpose of this specification is to ensure that system ar.d component / operability requirements or parameter limits are met before entry into an / operational condition for which these systems and components ensure safe / operation of the facility. This provision applies to changes in reactor / operating conditions or other specified conditions associated with plant / shutdown as well as startup. / t'nder the provisions of this specification, the applicable Surveillance / Requirements must be performed within the surveillance interval to ensure / that the 1.imiting 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 operational condition. / Specification 4.0.5 establishes the requirement 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 10 CFR 50.55a. These / requirements apply, except when relief has been provided in writing by / the Commission. / This specification includes clarification of the frequencies for / performing 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 consistenew in / surveillance intervals throughout the Technical Specifications and to / remove ambiguities relative to the frequencies for performing the / required inservice inspection and testing activities. / l'nder the terms of this specification, the more restrictive requirements / of the Technical Specifications take precedence 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 / a reactor operating condition or other specified condition takes precedence / over the ASME Boiler and Pressure Vessel Code provision which allows pumps / and valves to be tested up to one week after return to normal operation. / i l The Technical Specification definition of operable does not allow a grace / period before a component, that is not capable of performing its specified / function, is declared inoperable and takes precedence over the ASME Boiler / and Pressure Vessel Code provision which allows a valve to be incapable of / performing its specified function for up to 24 hours before being declared / l inoperable. / 1 l \\ l l 4-Id Amendment No. 130 l l'

I , 4,.1 INSTRL'MENTATXON AND CONTROL .e o e 3 y \\ Applicability k L-Applies to the reactor protective system and other critical instrumentation and controls. Objective 9 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 i be performed as specified in 4.1.1 and in Tables 4.1.1 to 4.1.3. 4.1.1 Overpressure Protection Systems Each PROV shall be demonstrated operable by: a. 1. Performance of a channel functional test on the PORV l 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 thereaf ter when the PORV is reouired operable. t 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 hours 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. l 4-le Amendment No. 130 I

~ TAB 11 4.1.1 Minf etas Fre<3uencies f or Oecks, Calibrations and Test ing of Reactor Protective System (5) SurveiIIarwe ChanneI lieseription hmction Frequency SurveiIIence Pkthod I. Power Range Safety G annels a. Check (7) S a. Ocuparison of four power channel readings. / b. Geck (3) D b. Channel adjustment to agree with heat belance calculation. Repeat whenever flus-AT power comparators alarms. c. Test M(2) c. Internal test signet. d. Calibrate (6) R d. G ennel alignment through measurement /edjustment of internal test points. 2.- IJide-Range Logarithmic a. Geck S a. Comparison of both wide-range readings. Neutron Monitors b. Test P b. Internal test signal. 3. Reactor Coolant Flow e. Oeck S a. Comparison of four separate total flow indicatione. b. Calibrate R b. Krmwn dif ferential preeeure applied to sensors. c. Test M(2) c. Bistable trip tester.(1)(4) 4 Thermal Margin /tw a. Oeck- (8) S a. Check: / Pressurizer Pressure (1) Temperature (1) Comparison of four separate calculated input trip pressure set point fadicatlans. (2) Pressure (2) Comparison of four pressurizer pressure Input indications. Same se 5(s) below.) b. Calibrate R b. Calibrate: (1) Temperature (1) Known resistance substituted for RfD coinci-Input dent with known pressure end power input. (2) Pressure (2) Part of 5(b) below. Input c. Test M(2) c. Blatable trip tester.(1) 5. Illgh-Pressurizer Pressure s. Geck (8) S a. Comparison of four seperate pressure fadications. / b. Calibrate R b. Known pressure applied to sensors. c. Test M(2) c. Bistable trip tester.(1) '-3 Amendment No. 30,66,118,130 t I I l l 1

_- l i TABLE 4.1.1 Minimum Frequencies for Oecks, Calibrations and Test ing of Reactor Protective System (5) (Contd) Surveillance manne1 Description Funetion Fretsency SurveiIIance Methad

6. Steam Cencrator Isvel a.

Check S a. Comparison of four level Indicat toms per generator. b. Calibrate R b. Knoem dif ferential pressure applied to sensors. c. Test M(2) c. Bistable trip tester.(1)

7. Steam Generator Pressure a.

Oeck S a. Comparisons of four pressure indications per generator, b. Calibrate R b. Known pressure applied to sensors. c. Test M(2) c. Bistable trip tester.(1)

8. Containment Pressure s.

Calibrate R a. Fnown 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 Protection System a.

Test M(2) a. Internal test circuits. Logic Units

12. Axial Shape Index (ASI) a.

Test R s. Known power inputs applied to lhermal Margin Calculator.

13. AT Power a.

Occk (7) S a. Same as 1(a). / l b. Check (3) D b. Same as f(b). 5 c. Test R c. Known temperature tapets applied to Thermal Margin Calculator. Amendment No. 30,66,118,130

c-- ,~ _ TAM E 4.1.1 ~ Ministen Frequencies f or Osecks, Calibrations and Test ing of Reactor Protective System (5) (Contd) Surveillance Channel TVscription Func t ion Frequency Surveillance Method

14. Thermal Margin Calculator a.

Dieck Q a. Verify constants. (1)1he bistable trip tester injects a signal into the bistable and provides a precision reedout of the trip set potet.

1. W711S:

(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 AT power until needout agrees with heat belance calculetions when above 1% et rated power. (4) Trip setting for operating pump combination only. Settings for other than operating pump combinettone emot le tested during routine monthly testing pes formed when shut down and within four hours af ter resuming operation with a different ouey cambination if the setting for that combination has not been tested within the previous sonth. (5)it is not necessary to perform the specified testing during prolonged periods in the refueling shutdoun condition if this occurs, cuitted testing will be performed prior to returning the plant to service. (6)Also includes testing variable high power function in the Thermal Margin Calculator. (7)Respsired if the reactor is critical. / (8) Required when PCS is > 1500 psia. / FREqlfENCY IW4ATION Notation Frequency S At least once per 12 hours. D At least once per 24 hours. li At least once per 7 days. N At least once per 31 days. Q At least once per 92 days. SA At least cace per 6 acaths. R At least once per 18 acnths. P Prior to eacle start-up if not done previous week. MA Mot applicable. 4-5 Amendment No. 30,118,130 y vv-- ec .s = y ,,py., ,,. + + _

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1 . ]. TAP,II 4.1.2 Minimess Frequeencies for Occks, Calibrations and Testing of Engf reered Safety Feature Instrinnentetton Controls Surveillance Omnnel Description Function Frequency Surveillance Mrthed 1. Iow-Pressure SIS Initiation s. Dieck S(4) a. Comparison of four seperate pressure Indicatione. / Channels b. Test (1) R b. Signal to meter relay adjust with test device / to verify SIS actuetion logic. c. Test M(2) c. Signal to meter relay adjusted with test device. 2. Iow-Pressure SIS Slanal Block a. Test (1) R a. Part of 1(b) above. Permissive and Auto Reset / 3. SIS Actuation Relays a. Test Q a. Steulat fon of SIS 2/4 logic trip using built-in test ing system. Both "etendby power" and "no l standby power" circuits will be tested for left - and right channels. Test will verify functioning l of initiation circuits of all equipment norselly operated by SIS stenals. l l b. Test R b. Complete automatic test initiated by same method i ( as Item 1(b) and including all normal automotic operatfons. 1 l 4. Containment High-Pressure a. Calibrate R a. Known pressure applied to sensors. Channels b. Test R b. Simulation of CHP 2/4 togic trip to verify actuotion logic for SIS, containment toolation and containment

spray, c.

Test M(2) c. Pressure switch operation simulated by opening or shorting terufnals or pressure apptled to the switch. 5. Containment High Radiation s. Occk D a. Cosparison of four seperated radiation level Channels indfcatfons. b. Calibrate R b. Exposure to known external radiation source. 4-6 Amendment No. 30,66,130 .~...

TARI.E 4.1.2 Minimum Frequencies for Checks, Calibrat f ons and Testing of Engineered Safety feature Instrumentation Controle (Contd) i Surveillance Channel Descriptton Functinn Frequency Surveillance Methnd i l l

13. Safety injection Tank level a.

Occk S a. Verify that level and pressure indication le and Pressure Instruments between Infic..i..t high high/ low alarme for level and pressure. b. Calibrate R b. Known pressure and diflerential pressere applied to pressure and level sensors. 14 Boric Acid Tank 1.evel Switches a. Test R a. Pump tank below low-level alare point to l verify switch operation. I 15. ~ Boric Acfd Heat Tracing System a. G eck D a. Observe temperature recorders for proper readings. 16. Mstn Steam Isolation Valve a. Geck S a. Coopere four t. 1c..i..t preeewre Indications. Circuits b. Test (3) R b. Signal to meter relay adjested with test device to verify MSiv ef tcuit logic. 17. SIRW Tank Temperature s. Geck M a. Compare i. ig.J;..; temperature reedouts. Indication and Alarme b. Calibrate R b. Known resistance appIled to indicating loop. 18 tow-Pressure Safety injection a. Oteck P Flow Control Valve CV-3006 Observe valve is open with air supply toelated. a. 19. Safety injection Bottle a. Oveck P a. Isolation Valves Ensure each valve open by observing valve yeaftfon indication and valve itself. Then lock open breakers and control power key switches. 20. Safety Injection Mintflow a. Occk P Valves CV-3027, 3056 Verify valves open and MS-3027 and 3056 poeltlened a. to maintain them open. M017.S: (1) 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 channe; at a time to prevent protectfon system actuation. (3)Ca11bration of the sensors is performed dur1ng c:;lIbration of Item 7(b), Table 4.1.1 (4) Required when PCS is > 1500 psia. / 4-8 Amendment No. 30,66,101,130

_x. m.,.._, ~' [ {... _," 'd _'f ' _~+ . j. TABIE 4.1.2 Mf nlanan Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrismentation Controle (Continued) / FREQlEf0fT II[frATIOff Notation Frequency S At least once per 12 hours. D At least once per 24 hours. %f 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 ueek. IIA Not applicable. 4-9 Amendment No. 30,130

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.k e ( 4.3 SYSTEMS SURVEILLANCE l: i APPLICABILITY l ~ \\ Applies to preoperational and inservice structural surveillance of the reactor vessel and other Class 1 Class 2 and Class 3 f system components. OBJECTIVE To insure the integrity of the Class 1. Class 2 and Class 3 piping systems and components. SPECITICATIONS a,b.c d - Deleted / L' i The Inservice Inspection program shall be reevaluated as e. required by 10 CTR 50. Section 50.55a(g)(5) to consider incorporation of new inspection techniques that have been I c proven practical, and the conclusions of the evaluation shall be used as appropriate to update the inspection program. f. Surveillance of the regenerative heat exchanr,er and primary ecolant 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 TSAR. The specimen removal schedule shall be as indicated in Table 4.3.3. E 4-16 Amendment No. 53,130 o

p L i L' I 4.3 SYSTEMS CL'RVETLLANCE (C:ntinred) 4 E h. Periodic leakage testing (a). (b) on each check valve listed / in Table 4.3.1 shall be accomplished prior 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 hours if such testing has not been accompitsbed within the previous 9 months and prior to returning the check valves to service af ter maintenance, repair or replacement work is performed on the valves. i. L'henever integrity of a pressure isolation valve listed in / 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.

L / (" 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. 53,72,130

f t io r t L l' 4.3 SYSTEMS SURVEILLANCE (Cont'd) K L _B_a _s i s f o The inspection program specified places major emphasis on the i areas of highest stress concentration as determined by general design evaluation and experience with similar systems.II) - In (- addition, that portion of the reactor vessel shell welds which will be subjected to a fast neutron dose sufficient to change 1 ductility properties will be inspected. The inspections will [ rely primarily on ultrasonic methods utilizing up-to-date analyzing equipment and trained personnel. Preoperational inspections will establish base conditions by determining indications that might occur from geometrical or metallurgical [ sources and from discontinuities in weldments or plates which might cause undue concern on a postservice inspection. To the extent applicable, based upon the existing design and construction of the plant, the requirements of Section XI a of the Code shall be complied with, Significant exceptions are detailed in the requests for relief which have received NRC approval and are contained in the Class 1, Class 2 and Class 3 Long-Term Inspection Plans. Reactor Vessel Surveillance Specimens Table 4.3.3 is consistent with the surveillance program as presented in the FSAR.(2) However, the withdrawal schedule has been modified to reflect the slightly different wall fluence values resulting from removal of the thermal shield. Valve Testing To ensure the continued integrity of selected check valves which are relied upon to preclude a potential LOCA outside containment, special requirements for periodic leak tests are specified. In addition a valve disk position check for the LPSi check valves is specified following each use of the LPSI system for shut.down cooling. This position check ensures that the four LPSI check valves have reclosed upon cessation of shutdown cooling flow. References 1 (1) FSAR, Section 4.5.6 (2) FSAR, Section 4.5.3 (3) Systematic Evaluation Program Topic V-11.A, NRC letter to y the licensee transmitting the final topic evaluation dated November 9, 1981. I i I 4-18 Amendment No. 53,72,130 December 21, 1982 6 Corrected 10/07/86 a}}