ML20244B543
| ML20244B543 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/19/1989 |
| From: | Newton R WESTINGHOUSE OPERATING PLANTS OWNERS GROUP |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20244B548 | List: |
| References | |
| OG-89-35, NUDOCS 8906130162 | |
| Download: ML20244B543 (667) | |
Text
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OG-89-35 l May 19, 1989-Mr. Charles E. Rossi Director Division of Operational Events Assessment ! Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D.C. 20555 ; Westinghouse Owners Group f~s)
Subject:
MERITS Technical Specifications and Bases (WCAP-12159) Review (d Transmittal 1
Reference:
- 1. NRC letter'from C. E. Rossi to R. A. Newton, NRC Review of the Westinghouse Owners Group MERITS Technical Specifications, April 28, 1989. i
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Dear Mr. Rossi. - The purpose of this letter is to forward Transmittal 1, which contains some of the information requested in Reference 1. Reference I requested additional-l - information to support the NRC's review of the MERITS Technical Specifications and Bases. Attachment I contains the response to' Item I with the exception of those MERITS !' specifications that were determined to require a revision to include. requirements based on the development of the reMaap. These revised ! specifications will be submitted.by May 22, 1903. j i Attachment 2 contains the complete response to Item 3. i g6230162890519 $. / n ^ {} / i
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i I 1 I Attachment 3 contains part of the response to Item 4. Based on the meeting held with the NRC on May 17,1989, the additional information required to respond to Item 4 will be submitted by May 30, 1989. In addition a draft CORE OPERATING LIMITS REPORT will be provided to the staff for their review. Responses to Items 2 and 5 will be provided by May 22, 1989. The software l l conversion requested by Item 6 will be provided by June 1, 1989, as requested j by the NRC. To facilitate NRC review,. future WOG responses to requests for information will be addressed to Mr. Mark Reinhart (Technical Specifications Branch), via the Document Control Desk, and will be signed by Ms. Jacqueline Hinds (Technical Specification Subcommittee Chairman). Responses will be submitted as soon as practical after receipt of the information requests from the NRC and they will be assembled in packages or grouped together whenever possible. If you have any questions on the information provided, please call me at (414) 221-2002. f i Very truly yours, 1 t . Roger A. Newton, Chairman Westinghouse Owners Group RAN/jrh Attachments I i i a 080lG _ _ _ _ _ _-_ ________-______-_- -_-___ _ - _ D
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L i cc: Mr. J.- A. Calvo - NRC l Mr. M. F. Reinhart .NRC Mr. J. B. George. .TU Electric Mr. M. R.'Edelman - Centerior Energy Mr. T. E. Tipton - NUMARC Mr. W. J. Hall - NUMARC Mr. R. A. Bernier. - Arizona Public Service Company
- Mr. R. R. Sgarro - Pennsylvania Power and. Light Mr. C. W. Smythe - GPU. Nuclear Corporation Mr. S. Webster.- Combustion Engineering Mr. J. Klaproth - General Electric Company
.: Mr; E. J. Lozito - Virginia Power Ms. J. R. Hinds - Pacific Gas. & Electric Company WOG Primary Representatives
~WOG Technical. Specifications Subcommittee Mr. J. A. Triggiani Mr. W. J. Johnson Mr. R. P. DiPiazza
.Mr. R. L. Bencini O .
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T M A Y - 1 8 '. 1989'- f ; ROSTER.OF CONTACTS FOR.THE' REVIEW OF PROPOSED NEW STANDARD TECHNICAL SPECIFICATIONS (STS) ; NRC STAFF REVIEW TEAM OEG NAME, _ TELEPHONE LOCATION j
~ Jose Ca lv e. : . rt'l llD 3 l OTSB Mark Reinhart (W STS/ALL 3 (c//<>i f -23139 11D12 )
Nanette Gilles'(RIII)'(W ) (815) 23-45451 BYRON- : Cal-Moon.-(W TS) 49-23136 :11D11
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Jim b i a-l c r ( n u T S )- 49-23137 11D13 J
.Millard Wohl (CE STS) 49-21181 11F21' l Bob Tjader (BWR STS)- 21187 11D 8 l John Schiffgens (B&W STS) 7C19 l 0&ds d &c$w II D 7 SRXB- Larry Phillips 49-25235 BE 7 Howard Richings 49-23234 8Ee9 ,
Larry Kopp- 49-20879 BB 4 'j Dan Fieno- ' 49-23238 BE 5 ;
- )
SICB Joe Joyce 49-23265 7E 7
, Iqbal Ahmed 49-20778 7E 8 .j SPLB Chang Li 49-20875 8F19 Thyagaraja Chandrasekaran (BWR) 49-20869 BD 6 !
Bill LeFave 49-20862 BC10 -l Charles Nichols 49-20854 BD12. 1 Peter Prescott 49-21011 10H12 l SELB Jim Knight- 49-20803 8D15 Jim Lazevnich 49-20814 8C16 ) John Knox 49-23285 BD13 j EMTB John Tsao 49-20937 9G15 l Barry Elliot 49-20931 9G20 ; l ECEB Frank Witt 49-20823 8A17 4 David 11ctley 49-20847 BH 8 EMEB Ken Dempsey 49-20918 9H 9
- Jai Rajan '49-20917 9G 8 ;
ESGB Sai P. Chan 49-20830 BG12 Gustaaf Giese-Koch 49-20836 BH23
)
PRAB Sammy Diab 49-21075 10B 2 ]' Jim Wing 10A 2 l FRFB . Wayne Meinke 49-23152 11C17 LHFB Rich Correia 49-21130 11G16
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T~ AHVl Q 0 eS TL oqS 115 IC, m4R K Re t tJ M A & "" 2 8 - 2989 PD John Monninger (PDIV Intern) 49-21374 13C16 PD Leon Engle (N. Anna P.M.) 49-21484 14H16 PD Ed Tomlinson~(PDIV'PE) (DG) 49-23024 13C15 PD Craig Harbuch (PDIV PM) 49-21337 13G22 PD Harley Silver (Crystal River PM) .49-21470 14G14 PD Les Kintner (Grand Gulf PM) 49-21458 14H 8 PD Larry Crocker (Hatch PM) 49-23049 '14D15 RI Lowell Tripp 346-5227 RI DER NAME TELEPHONE LOCATION RII Paul Frederickson 242-5649 BII RII Jim Caldwell (703) 894-5421 See Below. Senior Resident Inspector North Anna NRC Resident Inspector's Office Route 2, Box 78-A Mineral, Virginia 23117 l l RII Peter Holmes-Ray (905) 795-7677 See Below. Senior Resident Inspector Crystar River NRC Resident Inspector's Office 15760 W. Powerline Street
.. Crystal River, Florida 32629 -
RII Harold O. Christensen (601) 437-4620 See Below. Senior Resident Inspector Grand Gulf NRC Resident Inspector's Office Route 2, Box 399 Port Gibson, Mississippi 39150 RII John Manning (912) 367-9881 See Below. Senior Resident Inspector x Hatch 2 NRC Resident Inspector's Office l~ PcO. Box 725, Route 1 Baxley, Georgia, 31513 RIII Bill Forney 388-5590 RIII RIV Bill Seidle 728-8148 RIV RV Dennis Kirsch 463-3723 RV Phil Morrill _ _ _ _ 463-3728 RV r, LLNL Bob White 552-2169 LLNL J c Yf(> 353-5364 Germantown A t. D/ Leonard Reidinger - QE - b gg;p .,~..
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0G-89-35= I May 19, 1989 i ATTAC'HMENT I'. OVESTION SOURCE
-NRC letter from C. E. Rossi- to R.1 A. Newton, NRC-Review of the' Westinghouse Owners Group MERITS Technical.Specificaticas, April 28,'1989.
4 OVESTION REQUIRED INFORMATION-TO FULLY-PROGRESS WITH THE REVIEW OF THE WOG'S j
. PROPOSED NEW STS ,
}
- 1. Please provide.the staff with a comprehensive, marked up version of the-current Westinghouse STS which identifies. the following:
- a. The specific location in the new STS of requirements to be retained!
from the current STS but which now reside with a different LCO. This l information. should be detailed; for example,: show which LCO in the new - STS contains each instrument in Table 3.3-6,. RADIATION MONITORING ' INSTRUMENTATION FOR PLANT OPERATIONS from the current STS. This is an -i example; the staff needs this type _of. information for each 'similar - ; table, listing,- chart, etc.., found in the current STS. '
- b. The complete justification for not Lincluding-in. the new STS, .
O requirements that were to be retained. ~ As an example, Table:3.3-6 in . the current STS contains 16 instruments;-the new STS addresses 5 of ~ them. The. staff needs to know to where the requirements for the other .i 11 instruments are to be relocated and the basis for such relocation. j
- c. The preferred location for requirements which have been authorized for ;
relocation outside the new STS and which are not included in the H proposed new STS. This information should be detailed. See the j example in 1.a. above. ; i RESPONSE ! A comprehensive, marked up version of the current Westinghouse STS (Rev. 4a) is provided, in the attached binder, in response to the referenced questions. The i mark-up providesia detailed roadmap identifying the relationship.between 1 Sections 1, 2, 3, and 4 of the current STS and the corresponding Divisions 1, 2, and 3 of the MERITS Technical Specifications-(TS). This roadmap:together- : with its. amplifying notes, addresses the information requested in the three ' sections of Item 1. q O ; Page 1
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l j OG-89-35 ATTACHMENT.I f RESPONSE (continued) ; 1.a. The roadmap identifies the specific location in the MERITS TS of i requirements to be retained from the current STS but which now reside j with a different LCO. < 1.b. The roadmap clarifies the location of retained and relocated 3 requirements. In addition, the locations of justifications used in relocating requirements from the STS are more clearly identified. 1.c. The roadmap identifies the locations for requirements which have been , authorized for relocation outside the MERITS TS, but that will be 1 included in programs controlled by the Administrative Controls ~ .! r section. The WOG is unable to provide an explicit location for other l requirements. { l The WOG is unable to be specific since the member utilities utilize-different methods for maintaining and controlling requirements. One utility's FSAR may contain considerable more detail than another ! utility's FSAR. In-this case, the utility with the detailed FSAR may. , choose to relocate requirements to the FSAR. Another utility may ! already repeat some of.the present technical specification l g requirements in the plant procedures. Retaining the relocated ' 5 requirements in plant procedures may be the appropriate choice due to the minimal impact on the plant staff to implement MERITS. Consistent with the NRC interim policy statement, when licensees submit an amendment request to implement MERITS, they will identify the location of, and.contrels for the technica1'and administrative ; requirements of the removed Technical Specifications. l The WOG has identified the items to be considered when selecting a licensee-controlled document for maintaining a relocated ; requirement. Also, the WOG has stated the controls'that must be in place for maintaining the requirements. The criteria for selecting plant documents'and the controls for maintaining the requirements are
-as follows: i
! ' For Limiting Conditions for Operation 1
- The specified function (s) of the systems, components, or process variables for which the specification applies.
- The limits'which are placed on the operability of systems or components and on values of process variables, as conditions for operation.
- The modes for which the specified requirements are applicable.
- The remedial actions which are to be taken when the limiting condition for operation is not met.
[ ( i Page 2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .___ _ . _ _ . J
1 OG-89-35 May 19,-1989 .l ATTACHMENT 1 RESPONSE (continued) For Surveillance Requirements
- The means and frequency by which plant operators confirm by observation that~ the limits placed on system or component -
operability or values of process variables are as specified.
- The means and frequency by which plant operators or other plant 3 personnel confirm by specific actions such as test or inspections- !
t that' the limits on system or component operability are as -] specified. l Changes to the documents which include relocated requirements will be { controlled by the requirements of 10 CFR.50.59 (Changes, Tests, and <
' Experiments). This regulation allows changes in the facility or the l
procedures described in the FSAR without prior. Commission approval, 4 unless the proposed change involves an unreviewed safety question, or q requires a technical specification change. Licensees are required to: i maintain records of such changes which include written safety j evaluations providing the bases for the determination that the ! I changes do not involve an-unreviewed safety question. Annually, or at such shorter. intervals as maybe specified in the i license, a report containing a brief description of the changes, ! O ! including a summary of the safety evaluation of each, must be submitted to the NRC. To the extent that plant programs are described in the FSAR, changes to those programs can be made in. accordance with the requirements of 10 CFR 50.59, unless another l regulation is controlling (e.g.10 CFR 50.55a in the case of ISI/IST i Programs). j In addition to the 10 CFR 50.59, the JTS should include ; administrative requirements which provide for on-site and off-site- '{
- review group reviews and/or audits of 10 CFR 50.59, procedure, and l program changes affecting plant safety.
The types of plant documents that would meet this criteria include , but are.not limited to, the following: l Plant Operating / Surveillance Procedures. Final Safety Analysis Report
-Programs ;
! 'ISI/ISTprogram ) Process Control Program 1 ) Offsite Dose Calculation: Manual Fire Protection Plant i lO Page 3 i l ______________________=___________ ___________________ _ J
OG-89-35 RESPONSE (continued) The roadmap identified several requirements that were missed in the development of the MERITS TS. As a result, the revisions to those specifications containing missed requirements will be submitted by May 22,- 1989. MERITS TS With Missed Requirements To Be Revised
- 3.5.1 Containment Integrity l 3.5.2 Purge and Exhaust Isolation Radiation ~ Instrumentation 3.8.4 Containment Building Penetrations The roadmap also identified one requirement that was approved for relocation by the "NRC Staff Review of NSSS Vendor Owners Groups' Application of The Commission's Interim Policy Statement Criteria To Standard Technical Specifications," dated May 9, 1988 (NRC Split Report), but that was inadvertently retained in the LCO requirements for specification 3.6.11, . ..
Control Room Emergency Air Cleanup System. This specification will be revised to be consistent with the NRC Split Report and submitted at a later date. O . i i O O Page 4
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0G-89-35 j May 19, 1989 ( ATTACHMENT 2 OVEST10N SOURCE NRC letter from C:, E. Rossi to'R. A. Newton, NRC Review of the Westinghouse Owners Group MERITS Technical Specifications,' April 28, 1989. OVESTION' !. REOUIRED INFORMATION TO FULLY PROGRESS WITH THE REVIEW OF THE WOG'S L PROPOSED NEW STS
- 3. Changes to requirements as a result of generic letters must be implemented exactly and completely as described in the. generic letters. For example Generic Letter-88-16, which allows for the use of a Core Operating Limits Report-(COLR), provides a very specific section'
! to be.added to the administrative controls'section of STS. -- However, the proposed new STS includes only a statement that something should be. added to the administrative controls section; it does not include the
- details required by the generic letter. Since these details are mostly generic, they must be included in the standard.
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RESPONSE
The MERITS Phase 11 task did not include rewriting of the Standard Technical Specifications (STS) Sections 5.0,' Design Features, and 6.0, i 1 Administrative Controls. However, several changes made to the Limiting Conditions for Operation sectiocs (LCOs), and Surveillance Requirements (SRs) will result in additions te Sections 5.0 and 6.0 when rewritten during plant-specific implementriion of the MERITS Technical , Specifications. J Changes resulting from NRC Generic letters to Design Features and Administrative Controls are presented by subject / source in the following i pages. i The changes for the Design Features and Administrative Controls sections i ! have incorporated requirements for the COLR as described in Attachment 3 of { this transmittal. ' l I l i Page 1
OG-89-35 ATTACHMENT 2
Subject:
Fire Protection Requirements Source: Generic Letter 88-12 This is to be added to- Administrative Controls - [ UNIT REVIEW GROUP (URG)]: RESPONSIBILITIES: Review of the Fire Protection Program and implementing procedures and the submittal of recommended changes to the [ Company Nuclear Review and Audit Group]. This is to be added to Administrative Controls - PROCEDURES AND PROGRAMS: Fire Protection Program Implementation.- O . O . Page 2
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OG-89-35
Subject:
Core Operating Limits' Report
' Source: Generic Letter 88-16 This is to be added to Administrative Controls - REPORTING REQUIREMENTS:
CORE OPERATING LIMITS REPORT-Core operating limits shall be established and documented in the CORE OPERATING r LIMITS REPORT before each reload cycle or any remaining part of a reload cycle. (If desired, the individual -specifications that address core. operating limits may be referenced.) The analytical methods used to determine the' core operating limits shall be those previously reviewed and approved by NRC in:- T. WCAP-9272-P-A,
- WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",-
July 1985 (H Proprietary). (Methodology for LCO 3.1.2, McJerator Temperature Coefficient; LCO 3.1.4, Shutdown Bank Insertion Limit; LCO 3.1.5, Control Bank ~
- Insertion Limit; LCO 3.1.6A/B, Heat Flux Hot Channel Factor -
Fn(Z); LCO 3.1.7, Nuclear Enthalpy Rise Hot Channel Factor-FAH i y and,LC03.8.1,BoronConcentration).
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- 2. WCAP-9220-P-A[Rev.1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION", February 1982 (H Proprietary).
l (Methodology for LCO 3.1.6A/B, Heat Flux Hot Channel Factor - I Fn(Z).) _ 3a. WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES - TOPICAL REPORT", September 1974 (M Prop-ietary). (Methodology for LCO 3.1.8A, Axial Flux Difference - Constant Axial Offset Control.) - 3b. -T. M. Anderson to K. Kniel (Chiof of Core Performance Branch, NRC) January 31, 1980 --
Attachment:
Operation and Safety Analysis Aspects of an Improved Load Follow Package. (Methodology for LCO '3.1.8A, Axial Flux' Difference - . Constant Axial-f Offset Control.) _ l _ (continued) O Page 3
OG-89-35
;, - May 19, 1989 k ATTACHMENT 2 CORE OPERATING LIMITS REPORT (continued) 3c. NUREG-0800, Standard Review Plan, U. S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981. Branch Technical Position-CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev.2, July 1981.
(Methodology for LCO 3.1.8A, Axial Flux Difference - Constant Axial Axial Offset Control.) l 4. ' WCAP-10216-P-A,
- RELAXATION OF CONSTANT AX1AL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", June 1983 (W Proprietary).
(Methodology for LCO 3.1.88, Axial Flux Difference - Relaxed Axial Offset Control.) t - The core operating limits shall be determined so that ali applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident O analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. O Page 4 l _m___,______.-_-__-____s_- _ _ _ _ _ .
OG-89-35
, - . May 19, 1989
. ATTACHMENT 2
Subject:
Radiological Effluent Technical Specifications (RETS) ; i Source: Generic Letter 89-01 { This is to be added to Administrative Controls - PROCEDURES AND PROGRAMS: i: Radioactive Effluent Controls Proaram I ! A program shall be provided conforming with 10 CFR 50.36a for the control ) of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low 'as reasonably achievable.- The program (1) shall be contained in the ODCM, (2) shall be implemented by I operating procedures, and (3) shall include remedial actions to be taken j whenever the program limits are exceeded. The program shall include the following elements:
- 1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,
- 2) Limitations on the concentrations of radioactive material released in (N liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR 20, Appendix B, Table II, Column 2,
- 3) Monitoring 7 sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM,
- 4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR 50,
- 5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the i
' 0DCM at least every 31 days,
- 6) Limitations on the operability and use of the liquid and gaseous l '
effluent treatment systems to ensure.that the appropriate portions of l these systems are used to reduce releases of radioactivity when the. projected doses in a 31-day period would exceed 2 percent of the ! guidelines for the annual dose or dose commitment conforming to ! Appendix I to 10 CFR 50, I (continued) Page 5
OG-89-35 l May 19, 1989 1 I
#O ATTACHMENT 2 i
RETS (continued) f Radioactive Effluent Controls Proaram (continued)- Limitations on the' dose rate resulting from radioactive material / l 7) !_ released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR 20, Appendix B, Table- 3 j II, Column 1, B) Limitations on the annual and quarterly air doses resulting from noble l gases released in gaseous effluents from each unit to areas beyond the j ! SITE BOUNDARY conforming to Appendix I to.10 CFR 50,
- 9) Limitations on the annual and quarterly doses to a MEMBER OF THE -
PUBLIC from Iodine-131. Iodine-133, tritium, and all radionuclides in l particulate form with half-livas greater than 8 days in gaseous i effluents released from each unit to areas beyond the SITE BOUNDARY. conforming to Appendix 1 to 10 CFR 50,
- 10) Limitations on. venting and purging of the Mark II' containment through the Standby Gas Treatment ' system to maintain releases as low as reasonably achievable (BWRs with Mark II containments),
I
- 11) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle _. sources conforming to 40 CFR 190. ,
Radiological Environmental Monitorina PrQEIE ] A program shall be provided to monitor the radiation and radionuclides in i the environs of the plant. The program shall provide (1) representative ; measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and . modeling of environmental exposure pathways. The program shall (1) be I contained in the ODCM, (2)' conform to the guidance of Appendix I to 10 CFR 50, and (3) include the following:
- 1) Honitoring, sampling, analysis, and reporting of. radiation and I radionuclides in the environment in accordance with the methodology.
and parameters in the ODCM,
- 2) A Land Use Census to ensure that changes in the use~uf areas at'and 'i beyond the SITE BOUNDARY are identified and that' modifications to the I monitoring program are made if required by the results of this census, and 1
) 3) Participation in a Interlaboratory Comparison Program to ensure that ) independent checks on the precision and accuracy of the measurements l.. of radioactive materials in environmental sample matrices'are l performed as part of the quality assurance program for environmental monitoring. (continued). Page 6 l .
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I t 0G-89-35 RETS'(continued) These.are to replace Administrative Controls. sections with the same tities .in'- REPORTING REQUIREMENTS: ANNUAL RADIOLOGICAL ENVIRONMENTAL' OPERATING REPORT *' The Annual Radiological Environmental Operating Report covering the ' operation, of the unit during the previous calendar year.shall be submitted before Mayyl-of each year. :The report shall-include summaries, Interpretations,;and an
~
4 analysis of. trends of the results of the Radiological Environmental- Monitoring Program for the reporting period. The material provided shall be consistent-with the objectives outlined in'(1) the ODCM and (2) Sections.IV.B.2, IV.B.3,.
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and'1V.C of Appendix I to 10 CFR 50.
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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT" '
, The Semiannual Radioactive Effluent Release' Report Covering the operation of . .
the unit during the previous 6 months of operation shall be submitted within 60 days after January I and July,IJ of each year. . The. report shall include :n summary of.the: quantities of radioactive liquid;and gaseous effluents and solid waste released from the unit. The material provided shall:be (1)- consistent: O with the objectives outlined in the ODCM and PCP and-(2) in conformance withi' 10 CFR 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR'50. A single submittal may be made for a multi-unit station.
** A single submittal may be made for a multi-unit station. The submittal should combine those sections that are common to all units at the station; however,-for units with separate radwaste systems,~th submittal shall specify the releases' of radioactive material from each unit.
This is to be added to Administrative Controls- ' RECORD RETENTION (for:the-duration of the unit Operating License): Records of reviews performed for changes made to the DFFSITE DOS'E CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. O' (continued) i Page 7 %
i OG-89-35 May 19, 1989 i ATTACHMENT 2 i RETS (continued) These are to replace Administrative Controls sections with the same titles: PROCESS CONTROL PROGRAM (PCP) l Changes to the PCP: ! a. Shall be documented and records of reviews performed shall be retained i as required by Specification [ ]. This documentation shall contain: ;
- 1) Sufficient information to support the change together with the -l appropriate analyses or evaluations justifying the change (s) and j l 2) A determination that the change will maintain the overail -
I conformance of the solidified waste product to existing ' ! requirements of Federal, State, or other. applicable regulations.
- b. Shall become effective after review and acceptance by the [URG] and )
the approval of the Plant Manager. J ( l
\ i 0FFSITE DOSE CALCULATION MANUAL (ODCM) ]
Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained I
as required by Specification [ ]. This documentation shall ; contain , 1
- 1) Sufficient information to support the change together with the ,.
appropriate analyses or evaluations justifying the change (s) and i
- 2) A determination that the change will maintain.the level of j
. radioactive effluent control required by 10 CFR 20.106, i 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10'CFR 50 and not i adversely impact the accuracy or reliability of effluent,' dose, or setpoint calculations. i
- b. Shall become effective after review and acceptance by the [URG) and-L the approval of the Plant Manager.
l c. Shall be submitted to the Commission in the form of a complete, i legible copy of the entire ODCM as a part of or concurrent with the i Semiannual Radioactive Effluent Release Report for the period of the l report in which any change to the ODCM was made. Each change shall be l ( identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented. Page 8
0G-89-35 ATTACHMENT 3 00ESTION SOURCE NRC letter from C. E. Rossi to R. A. Newton,.NRC Review'of the Westinghouse Owners Group MERITS Technical Specifications, April 28, 1989. NRC MEETING WITH THE WOG The WOG met with the NRC Staff on May 17, 1989 to discuss the Reactor Chapter and parameter limits to be contained in the Core Operating Limits Report. OVESTION l RE0VIRED INFORMATION TO FULLY PROGRESS WITH THE REVIEW OF-THE'WOG'S PROP 05fD NEW STS
- 4. Associated with the example used 'in . item 3 above, Generic Letter 8S-16 is not intended to place Safety Lintits in a COLR, and it is not intended to place parameters which are not currently cycle specific in a COLR.
With respect to the WOG's proposed new STS, the staff position is that the e following parameters should not be relocated to a COLR since they are not ( cycle specific. Therefore, the WOG should provide complete technical ' specifications for these parameters.
- a. Safety Limit 2.1.1, Reactor Core Safety Limit.
- b. LC0 3.1.2, Moderator Temperature Coefficient (MTC). '
- c. LCO 3.3.3, RCS Pressure / Temperature Limits. "
- d. LC0 3.4.1 c, ECCS Accumulators boron concentration.
- e. LCO 3.4.5 b, ECCS RWST boron concentration. ;
- f. LC0 3.8.1. REFUELING-0PERATIONS Boron. Concentration.
For other parameters proposed to be included in a COLR, the new STS must l provide the specific references to NRC-approved methodologies used to l develop the respective parameters. Generic Letter 88-16 requires that the specific references " identify the Topical Report (s) by number, title, and date, or identify the staff's safety evaluation report for a plant-specific , methodology by NRC letter and date." As mentioned in ites 2 above, an ! NRC-approved, plant-specific methodology, by itself, does not constitute an J F NRC-approved, generic methodology. The new STS should also make it clear that individual plants have the option of retaining cycle specific parameters in their TS-even if approved methodologies for their plant exists. O Page 1
_7,______ ,
, .i OG-89-35 OUESTION-(continued)?
- As an alternative, it may be more practical to retain all of the parameters in the body of the new STS and to identify.the COLR option for plant. .
-specific submittals. .With this' alternative, submittal of the.COLR-and i referenced NRC-approved methodologies could be' deferred until.the. lead -
plant.submittals. MEETING CLARIFICATION COMMENTS-A number of MERITS TS will be revised as a' result:of comments.from the - meeting'with the NRC staff on May 17, 1989. .The specifications which include references to the COLR will be revised to-incorporate the comments :1 0 from this meeting and will be submitted by the May'30, 1989' commitments date. 1 3 J
RESPONSE
Table I was developed based upon the results of the meeting with the _NRC. .It . contains a' list of the parameter limits'that will now be!provided in the COLR,
.along with the number of the MERITS Technical Specifications'that include the parameter and a reference to' the: documents in Table 2 containing the associated 9' O calculation methodology for each parameter.
For specifications 3.1.4, 3.1.5, 3.1.8A, and 3.1.88, the Revision A. version submitted in the MERITS TS is correct and based upon,the. discussion at the NRC .; meeting, no further. actions.are necessary at this time.. .q For specifications 3.1.2, 3.1.6A, 3.1.6B, 3.1.7,~and 3.8.1, changes must be i made to incorporate the comments from the NRC meeting.- Revisions are being prepared and the revised specifications will- be submitted to the' NRC by May 29, 1989. The three MERITS TS with parameter limits no longer proposed for inclusion:in i the COLR, specifications 2.1.1, 3.4.1, and.3.4.5, will be revised and submitted by Nay 22, 1989. Specification.3.3.3, RCS Pressure / Temperature Limits, will be revised an'd . ! submitted to the NRC at- a later date after a WOG decision:has: been made on the j preferred mechanism to address this issue. q A draft COLR report will. also be developed and submitted to the NRC by. j i May 29, 1989. l The revisions described above have also been incorporated into the additions for Division 5,0 submitted in Attachment 1 of this transmittal. LO Page 2
i OG-89-35 1
,- May 19, 1989 ;
ATTACHMENT 3-Table 1 . Core Operating Limit Report Parameter Limits- i MERITS Technical Table 2 - l Specification Reference Number Parameter Number > 3.1.2 Moderator Temperature Coefficient 1 3.1.4 Shutdown Bank Insertion Limit 1 l 3.1.5 Centrol Bank Insertion Limit I-3.1.6A/B Heat Flux Hot Channel' Factor 1 and 1
- 2a or 2b or 2c '
I 3.1.7 Nuclear Enthalpy Rise Hot l' Channel Factor 3.1.8A/B Axial Flux Difference . f~ Constant Axial Offset Control 3a, 3b, 'and 3c ! ( Relaxed Axial Offset Control 4-3.8.1 _ Boron Concentration 1 4 l O Page 3
_ m . .- . 1 OG-89-35 ATTACHMENT 3-Table 2 Core Operating Limit Report References l
- 1. WCAP-9272-P-A, " WESTINGHOUSE RELOAD. SAFETY EVALUATION METHODOLOGY",
July 1985 (W Proprietary).
]
I 2a. WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 ,l VERSION", February 1982 (M Prop 1etary). l 2b. WCAP-9561-P-A, ADD. 3, Rev..., "BAR'T A-1: A ".0MPUTER CODE FOR THE BEST l ESTIMATE ANALYSIS OF REFLOOL TRANSIENTS- SPEi,IAL REPORT: THIMBLE { MODELING IN H ECCS EVALUATI0n MODEL", July,1986, (W Proprietary). j 2c. WCAP-10266-P-A Rev.2, "THE 1981 YERSION OF WESTINGHOUSE EVALUATION- l H0 DEL USING BASH CODE", March 1987, (H Proprietary)._ s ys 3a. WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES I - TOPICAL REPORT", September 1974 (M Proprietary). 3b. T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC) January 31, 1980 --
Attachment:
Operation and Safety Analysis Aspects of an Improved Load Follow Package. 3c. NUREG-0800, Standard Review Plan, U. S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981. Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev.2, July 1981.
- 4. WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEI' t..ANCE TECHNICAL SPECIFICATION", June 1983 (M Proprietary).
l . l O Page 4
LIST of ROADMAP NOTES (continued)
- 9. These are Radiological Effluent Technical Specification (RETS) monitors.
These instruments provide no safety-related functions. They only provide indication and/or alarms to alert the control room operators to a potential r-ndiological hazard. As such, they are to be relocated to the PROCESS CONTROL PROGRAM in accordance with Generic Letter 89-01.
- 10. The containment parameters - P,, La ' E d' lt - have been relocated.
They will be added to the list of other containment parameters in the Design Features Division.
- 11. This technical specification, with its requirements, actions, and surveillance, is incorporated into Technical Specifications 3.1.7(FAHb and 3.3.1 (RCS flow rate).
- 12. This technical ~ specification, with its requirements, actions, and surveillance, is incorporated into MERITS as Technical Specification 3.1.9.
- 13. The shield building structural integrity is not required to support the retained MERITS LCO 3.5.1 because LCO 3.5.1 only requires containment leak tightness and because the shield building is not made of pre-stressed concrete. Therefore the surveillance have not been retained withic the technical specifications.
- 4. In Rev.B of Technical Specification 3.5.1 (to be provided later)
Surveillance Requirement, SR 3.5.1.9, assures that the containment structural integrity surveillance requirements for prestressed concrete containments is performed. The Containment Structural Integrity Test Program will be provided as an Administrative Controls Division paragraph. The test program will contain the prestressed concrete test requirements currently found in STS 3.6.1.7, Containment Structural Integrity.
- 15. This is a Fire Protection specification. This specification is incorporated in either the plant Fire Protection Plan or Procedure in accordance with Generic Letter 86-10.
- 16. The surveillance requirements will be included in a Steam Generator Tube Inspection Program which will be provided as an Administrative Controls Division paragraph. .
- 17. The surveillance requirements will be included in a Reactor Coolant Pump Flywheel Inspection Program which will be provided as an Administrative Controls Division paragraph.
- 18. In our review of the STS it was discovered that Technien1 Specifications 3.5.2 and 3.8.4 did not include these requirements. New Technical Specifications are in preparation.
9
Docket No. 50-445 1.0 DEFINITIONS August 14, 1987 I Mt D e rf os .1 i on , A Sub toi v 1,u o herw oe noW . The defined terms of this section appear in capitalized type and are applicable I throughout these Technical Specifications. ACTION Jd ACTION shall be that part of a Technical Specification which prescribes remedialmeasuresrequiredunderdesjgnatedconditions. 4 ACTUATION LOGIC TEST i k An ACTUATION LOGIC TEST shall be the application of various simulated ! input combinations in conjunction with eacti possible interlock logi_c state and j
. verification of the required logic output. The ACTUATION 1AGIC TEST shall i include a continuity check, as a minimum, af output devices.
- l ANALOG CHANNEL OPERATIONAL TEST l
. j pl An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated i signal into the channel as close to the-sensor as practicable to verify OPERABILITY of alars, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, inter-lock and/or Trip Setpoints such 'that the setpoints are within the required !
range and accuracy. ( AXIAL FLUX DIFFERrNCE , j Jd AXIAL FLUX DIFFERENCE shall be the difference in normalized flux' signals between the top and bottom halves of a two rection excore neutron detector. CHANNEL CALIBRATION j Idi A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to knwn ! values of input. The CHANNEL CALIBRATION shall encompass the entire channel l including the sensors and alars, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. CHANNEL CHECK , j k6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. . This' determination shall include, where possible, comparison.of the channel indication and/or status with other indications and/or status derived from independent _instryment channels measuring the same parameter. MC0HANCHEPEAK-UNIT 1 1-1
Socket No. 50-445 DEFINITIONS August 14, 1987 5 CONTAINMENT INTEGRITY 44 CONTAINMENT INTEGRITY shall exist when: as All penetrations required to be closed during accident conditions q are either:
- 1) Capableofbeingclosedbyan5PERABLEcontainmentautomatic isolation valve systas, or j
- 2) Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in I Table [3.5-1]cfspecification[3.6.33 .
.l
- b. All equipment hatches.are closed and sealed, c.- Each air lock is in compliance with the requirements of Specification
- {3.6.1.3], -
- d. The containreent leakage rates gre within the Itaits of Specification
[3.6.1.2],and ) i
- e. The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.
/ CONTROLLED LEAKAGE bet e ud s. Le Ls4 Su:.~tt- 3 de * ~2- % l F}4 CONTROLLED LtAKAGE shall be that seal water flow supplied to the reactor 1
a oolant pump seals. - I l CORE ALTERATIONS j 2d CORE ALTERATIONS shall be the movement or annipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement ef a component to a safe conservative position. DOSE EQUIVALENT I-131 latf 00$E EQUIVALEKT 1-131 shall to that concentrutten of I-131 (microcuria/ gram) i which alone would produce the same thyroid dose as the quantity and isotopic ! sixture of I-131,1-132,1-133,1-134, and I-135 actually present. Tim thyroid j dose conversion factors used for this calculation shall he those listed in : [ Table III of TID-14844, " Calculation of Distance Factors for Power end Test l Reacter Sites" or Table E-7 of NBC Angulatory Guide 1.109.' Revision 1, October 1977). I - AVERAGE DISINTEGRATION ENERGY LAf I shall be the average (weighted in proportion to the concentration of each radionuclides in the sample) of the sum of the average beta and gauna energies per disintegration (MeV/d) for the radionuclides in the sample.
/COMANCHEPEAK-UNIT 1 1-2
l
~
Docket No. 50-445 DEFINITIONS ' ' ENGINEERED SAFETY FEATURES RESPONSE TIME d The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment-is capabit of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include - diesel- generator starting and sequence loading delays.uhere applicable. FREQUENCY NOTATION D ele. w pv S A hc4v~ (.o, M - I1AS The FREQUENCY NOTATION specified for the performance of Surveillance 1 Requirements shall correspond to the intervals defined in Table 1.1. J IDENTIFIED LEAKAGE ,
)
1.14 IDENTIFIED LEAKAGE shall be:
- a. ' Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are .:aptured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere free sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systass or not to be PRESSURE BOUNDARY
[ LEAKAGE, or ,
- c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.
MASTER RELAY TEST 1:I5 A MASTER RELAY TEST shall be the energiration of each anster relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay. 1 MEMBER (5) DF THE PUBLIC l; 1-28 IEEER(5) 0F 1NE MSLIC shall inchute all persons the see art occupa-tionally associated with the plant. This category does est include amployees of the licensee, its contractors, or .wendors. Also' excluded from this category are persons who enter the site to service equipment or to aske deliveries. - This category does include persons who use portions of the site for recre-stional, occupational, or other purposes act associated with the plant. VFFSITE ODSE CALCULATION MANUAL 2d7 The DFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and paramew.s used in the calculation of offsite doses due to radioactive
- gaseous and ,1iquid1rffluents, in the t:alculation of gaseous and liquid effluent monitoring Alars/ Trip Setpoints, and in $he conduct af the Er.dron-h aantal Radiological Monitoring Program.
/ COMANCHE PEAK - UNIT 1 1-3
Docket No. 50-445 DEFINITIONS August 14, 1987 OPERABLE - OPERABILITY kilf' A system, subsystem, train, component or oevice shall be OPERABLE or have OPERABILITY when it is capable of perfoming its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem,. train, component, or device to perform its function (s) are also capable of perfoming their related support function (s). OPERATIONAL MODE - MODE - I htt An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power 1r, vel, and average-reactor coolant temperature specified in Table 1.2. -
~
PHYSICS TESTS 1
.1M PHYSICS TESTS shall be those tests T-. A. d to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:
(1) described in Chapter [14.0] of the FSAR, (2) authorized under tha provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission. l PRESSURE BOUNDARY LEAKAGE
,hf1 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube.
I leakage) through a nonisolable fault in a Reactor Coolant System component. body, pipe wall. or vessel' wall. 1 PROCESS CONTROL PROGRAM -' j . kf'l The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, I sampling, analyses, tests, and determinations to be ande to ensure that ' processing and packaging of solid radioactive wastas based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20. El, and 71'and 'l Federal and State regulations, burial ground mquirements and other require- ' ments governing the disposal of radioactive wasta. PURGE - PURGING . j l t27 PURGE or PURGING shall to any controlled Imucets of discharging air or gas from a confinement to maintain temperature, pressure, busidity, concentration or other operating condition, in such a manner that replacement air or gas is required to. purify the confinement.
/COMANCHEPEAK-UNIT 1 1-4
i i Docket No. 50-445 DEFINITIONS August 14, 1987 ; I ! QUADRANT POWER TILT RATIO W QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore , detector caltbrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximus lower excore detector calibrated j output to the average of the lower excore detector calibrated outputs, whichever i is greater. With one excore detector inoperable, the remaining three detectors I shall be used for computing the average. ; RATED THERMAL POWER , 4 k25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to i the reactor coolant of W t. - REACTOR TRIP SYSTEM RESPONSE TIME L2fr The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from j when the sonitored parameter exceeds its Trip Satpoint at the channel sensor until loss of stationary gripper coil voltage. ; REPORTABLE EVENT
.1d 7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.
D=.h. WA, p er Toskhc~+A t0 aku it . L- LI O 105 ( pHIELDBUILDINGINTEGRITY lair SHIELD BUILDING INTEGRITY shall exist when: ;
- a. Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, then at least one door shall be closed,
- b. The Shield Building Filtrstion System is DPERABLE, and
- c. The sealing mechanism associated wi3 each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.
SHUTDOWN MARGIN 1 4 SHUTDOWN MARGIN shall be the instantaneous andW t of reactivit; by which the reactor is suberitical or would be suberitical from its present condition assuming all full-length rod cluster assemblies (shutdown and contal) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE BOUNDARY g The SITE BOUNDARY shall be that line bwyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. - 's COMANCHE PEAK - UNIT 1 1-5
Oocket No. 50-445 DEFINITIONS August 14, 1967 O SLAVE RELAY TEST l J M r A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include
'a continut.ty check, as a minimum, of associated testable actuation devices.
SOLIDIFICATION q, tW p ,- khhh 9 $
, i " .13 4 SOLIDIFICATION shall be the conversion of wet wastas into a form that -
meets shipping and burial ground requirements. SOURCE CHECK Feff A SOURCE CHECK shall be the plitative assessment of. channel response f when the channel sensor is exposed to a source of increased radioactivity. STAGGERED TEST BASIS g A STAGGERED. TEST BASIS shall consist of:
- a. A test schedule for n systems, subsystans, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and
- b. The testing of one system, subsystem, train, or other designated
( component at the beginning of each subinterval. , THERMAL POWER j 1 JeSi THERMAL POWER shall be the total reactor more heat transfer rate to the ! reactor coolant. ' TRIP ACTUATING DEVICE OPERATIONAL TEST 1rtif A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the l Trip Actuating Device and verifying OPERABILITY of alai, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates
-at the required setpoint within the required accuracy. ,
i UNIDENTIFIED LEAKAGE
,Ft37 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
D COMANCHE PEAK - UNIT 1 1-6
Docket No. 50-445 DEFINITIONS 9"St II' iib 7 ' 1 UNRESTRICTED AREA
]
2 E An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection'of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. Delch pn L3b b uM i.o i r-ENTILATION
.V EXHAUST TREATMENT SYSTEh* h 14 j I bM A VENTILATION EXHAUST TREATMENT SYSTEM shall be arty system designed and installed to reduce gaseous radiciodine or radioactive material in particulate fors in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing fodines or particu -
lates from the gaseous exhaust stream prior to the release ta the environment. Such a system is not considered to have any effect on mobis gas affluents. * ! i Engineered Safety Featres Atmospheric cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM camponents. VENTING -
. 1 L40- VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not pro-
- vided or required during VENTING. Vant,. used in system names, does not imply a VENTING process. ,
Dele M Fw 3 0 IWASTEGASHOLDUPSYSkEMk hwh *Lo # de%is h*r A WASTE GAS HOLDUP SYETEM shall be any system designed and installed to ' reduce radioactive gaseous affluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and prov' ding for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. - L m' e
!COMANCHEPEAK-UNIT 1 1-7
. . 4
~
'l gg g , g 9 v- Tush cd- ,i b' Docket No. 50-445 August 14, 1987 TEE 3d
,( FREQUENCY NOTATION NOTATIOS FREQUENCY
$ At least once per 22 hours. I D At least once per 24 hours. -
)
W , At least once per 7 days. M At least once per 31 A ys.
; Q At least once per 32 A ys.
4 i SA At least once per W dgys. j I R At least once per 28 months. i l S/U . Prior to each reactor startup. I N. A. Not applicable. I j P Completed prior to each release. j L ! l . N 4 1 4 e
.9 I
~
/COMANCHEPEAK-UNIT 1 1-8
TWe i. \ '
- Docket No. 50 445 TABLE 1.2 August 14, 1987 n' !
OPERATIONAL MODES REACTIVITY E RATED . AVERAGE COOLANT MODE CONDITION. K;ff THERMAL POWER
- TEMPERATURE
- 1. POWER OPERATION 1 0.99 > 55 1 350*F
- 2. STARTUP > 0.99 1 55 1 350*F
- 3. HOT STANDBY < 0.99 0 1 350'F
- 4. HOT SHtJTDOWN < 0.99 0 350'F > T
> 200'F avg
- 5. COLD SHUTDOWN < 0.99 0 5 200'F
- 6. REFUELING **- e 0.95 0 3 140'F
" Excluding decay heat.
g^ ** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
~
e e W 1 YCOMANCHEPEAK-UNIT 1 1-9
1
~
Docket No. 50-445 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS August 14. 1987
; _ $ L 1.1.1 2.1 SAFETY LIMIT,5 . :
~
REACTOR CORE l - 2.1.1 The combination of THERMAL POWER, pre'ssurizer pressure, and the highest operating loop coolant temperature (T,,,) shall not exceed the limits shown in l Figures 2.1-1 and 2.1-2 for a and n-1 loop operation, respectively. l
~ '
APPLICABILITY: DODES 1 and 2. I ACTION:
- cou ziTica A ,
tfhrnever the point defined by the combination of the highest operating loop average temperature and THERMAL p0WER has exceeded the appropriate pressurizer i pressure line, be in HDT STAND 8Y within 1 bour, and comply with the require-ments of Specification 5.7.1.
' l 1
REACTOR COOLANT SYSTEM PRE'55URE st.ca.1 2.1. 2 The Reactor Coolant System pressure shall not exceed [27353 psig. l APPLICABILITY: DCDES 1, 2, 3, 4, and 5. II ACTION: , Y --- c..uomeo n MODES 1 and 2: tihenevertheReactorCoolantSystaspressurehasexceeded(2735]psig,be l in HOT STANDBY with the Reactor Coolant System pressure within its limit i within I hour, and comply with the requirements of specification 5.7.1. j Co u ntnu M 13 ICDES 3, 4 and 5: tihenever the Reactor Coolant Systas pressure has exceeded [27353 psig. reduce the Reactor Coolant System pressure to within its limit within 5 minutes, and comply with the regtirementa of Specification 5.7.1.
~
8 4
. i
! CDMANCHE PEAK - UNIT 1 2-1 e
Socket No. 50-445 August 14, 1987 9 4 e \ . . O e M H GURE 2. M , REACTOR CORE SAFETY LDt!T - FOUR LOOPS IN OPERAUDN COMANCHE PEAK - UNIT 1 2-2
Docket No. 50-445 August 14, 1987 e e e e
- O e
e
- i e-l l
e e I i ( I i f ' FIGURE 2.1-2 REACTOR CORE SAFETY LIMIT - THREE LOOPS IN OPERATION COMANCHE PEAK - UNIT 1 2-3
t I l 4 Docket No. 50-445 ; August 14, 1987 i SAFETY LIMITS AND LIMITING SAFETY. SYSTEM SETTINGS i J 3A . TAUT 6/rbEnf7*ATioN 2.2 (4"ITIE 5AFE" SYSTE" Se"!MS
- 321 !
REACTOR TRIP SYSTEM 6 2.2.1 The Reactor. Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip 5etpoint values shown in Table 2.2-1. AA.s -/ APPLICABILITY: As shown for each channel in Table 3.3-1. 3.2. 2 -/ 1 ACTION:
-belek<l See L,co 2.2.1 Tos7gjgmu y,w sr 7r
. a. Wie : a reter . S ';:* ...__ r ::^__ .r er _ -? d 5:t '-t
?r erre"-t i=a *"- t'- --!-- Pr - S t'- T '; Se*-4-t ee!r-ht = : :==rnti= the W =?= 'n- 8: 5 ^'?r -2 1: Y:1 =
celr ef Tel 2.2-1, adjet W ::t;-'-t ' z-' tzt r"l the TM; n' e'-t =! r.
- b. With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Values-column o,f Table 2.2-1, either: l
^df"st Deleted tM se+-ei-t see LCo 3-er-i@EjF3_ 2.1 ATrtN '[t.,m
- 1. _ _ - - th t' . M**3 e 4'it "e?r ef Td'- 2. 2-1 rd d-t:ri-- Tithie l? "-! t'St E'"'"ti"- 2 ?-l -
1
& er setisfied fe- t'- eff--t-d eM- :1, ee Y 221-1 i
- 2. Declare the channel inoperable and apply the applicable ACTION j statement requirement of Specification 3.3.1 until the channel 1
, is restored to 0PERABLE status with its setpoint adjusted consistent with the Trip Jetpoint value.
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O e SECTIONS 3.0 AND 4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
\
I a O e O o e b
- A d 4-
,, e S
D l ySTS- ., 3/4 0 o
. a -
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4. 0 APPLICABILITY LIMITING CONDITION FOR OPERATION Ic.c 3.o.L
- 3. 0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements.shall be met.
" L c.o 3 .c. t 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.
Sompletion of the ACTION requirements is not required. L.c c 3 .0 3 3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within I hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:
- a. At least HOT STANDBY within the next 6 hours,
- b. At least HOT SHUTDOWN within the following 6 hours, and
- c. At least COLD SHUTDOWN within the subsequent 24 hours.
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. Lhis specification is not applicable in MDDE 5 or 6.
LC.O 3.0 4 '
3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the conditions for the Limiting. Condition for Operation are met without reliance on provisions contained in the ACTION requimments. This provision shall not prevent passage through or to OPERATIONAL DODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications.
!WSTS 3/4 0-1
APPLICABILITY 4 SURVEILLANCE REQUIREMENTS
~5R 3.0. I 4.0.1 5arveillance Requirements shall be met during the OPERATIONAL MODES l or other conditions specified for individual Limiting Conditions for L
Operation unless otherwise stated in an individual Surveillance Requirement.
.5R.3c.2.
4.0.2 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, but '
- t. The combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance
- interval.
~ S R 3.c. 3 ~
4.0.3 Failure to perfore a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting condition for Operation. Exceptions to these requirements are stated in the individual specifications. Surveillance Requirements do not have to be performed on inoperable equipment. 5 R 3.o.4
+
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be ( made unless the Surveillance Requirement (s) associated with the Limiting ' Condition for Operation has been performed within the stated surveillance interval o. as otherwise specified. . s R 3.o.s-4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
- a. 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 Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g), except where specific written-
~
relief has been granted by the Commission pursuant to 10 CFR Part 50 Section 50.55a(g)(6)(1); - V \ l hSTS. 3/4 0-2 I 1
. - i
1 APPLICABILITY Y.J SURVEILLANCE REQUIREMENTS (Continued) L 3 R 3.0.5
- 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 Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies for Code and applicable Addenda performing inservice
. terminology for inservice inspection and testing inspection and testino activities activitiet Weekly At least once per 7 days Monthly At least once per 31 days 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
- c. The provisions of Specification 4.0.2 are applicable to the 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 Surveillance Requirement's; and
~
- e. Nothing in the ASME Boiler.and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
S i [WSTS 3/4 0-3
4
, 3/4.1 REACTIVITY CONTROL SYSTEMS
( 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - 1 , GREATER THAN 200'F - LIMITING CONDITION FOR OPERATION
.__., L C O 3.1.1 3.1.1.1 The SHUTDOW MARGIN shall be greater than or equal to [1.6%) Ak/k lfor[n]loopoperation. '
APPLICABILITY: MODES J1, 2*,' 3, and 4. ACTION:
,-. c.caa j rior) A U SM
- Wb With the SHUTDOW MARGIN less than [1.6%3 Ak/k, immediately initiate and continue boration at greater than or equal to gpm of a solution containing greater than or equal to ppa boron or equivalent until the required SHUTDOW MARGIN is restored.
I SURVEILLANCE REQUIREMENTS - 4.1.1.1.1 The SHUTDOW MARGIN'shall be detemined to be greater than or equal
*
- 30 '
$R 3.2.1.L a Lco S. l. S
- a. Within I hour after detection of an inoperable control rod (s) and at least once per 12 hours thereafter while the rod (s) is inoperable.
If the inoperable control rod is immovable or untrippable, the above required SHUTDOW MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the innovable or untrippable -- control rod (s); .
- p/C3. t. S'. t,
- b. When in MODE 1 or MODE 2 with K,ff greater than or equal h1 at least once per 12 hours by verifyi that control hank withdrawal is ;
within the limits of Specification .1.3.6; i rpK 3.1. S.1 !
- c. When in MODE 2 with K,ff less than 1, within 4 hours prior to, . l achieving reactor criticality by verifying that the predicted critical control rod position is within the limits ofl Specification '
3.1.3.6; e gt 6 e d ut ,,A A tu:L. w .,4 c , v.4 & .
- d. Prior to initial operation above 7% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specifica-tion 4.1.; 1.le. below, with the control banks at the maximum inser-tion limit of Specification 3.1.3.6; and r
OSee Special Test Exceptions Specification 3.10.1.
~
- h .tc A J p p h j h L C o 3.1.1 LL a. B V W STs 3/4 1-1
I l REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
; $ R 3.t.t.1 ,
!e. When in MODE 3 or 4, at least once per 24 hours by consideration of the following factors: l l j
- 1) ' Reactor Coolant System boron concentration,
- 2) Control rod position,
. . j
- 3) Reactor Coolant System average temperature, '
- 4) Fuel burnup based on gross thermal energy generation, 1
- 5) Xenon concentration, and ,
\
- 6) Samarium concentration.
- om ppKph Lto 3. l.1 A 9 -
4.1.1.1.2 The overall core reactivity balance shall be compa n d to
' predicted values to demonstrate agreement within 11% Ak/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification [4.1.1.1.le.), above. The predicted reactivity values shall be adjusted (normalized) to correspond to e the actual core conditions prior to exceeding a fuel burnup of 60 EFPD
( after each fuel loading.
- 9 4
e e t i 6
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- k. -
l
/ w STs 3/4 1-2
' 1 j
l
REACTIVITY CONTROL SYSTEMS (/ SHUTDOWN MARGIN - T,y LESS THAN OR EQUAL TO 200*F LIMITING CONDITION FOR OPERATION
- L c. o S.t.l 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to 2% Ak/k.
APPLICABILITY: MODE 5. - ACTION:
; ComiTW A With the SHUTDOWN MARGIN less than 1% Ak/k, immediately ittitiate.and continue boration at greater than or equal to gpm of a solution containing greater than or equal to ppm boron or aquTIaTent until the required SHUTDOWN MARGIN is restored.
~
SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal
$ R 3.l. i.h
- a. hithin I hour after detection of an inoperable control rod (s) and at least once per 12 hours thereafter while the rod (s) is ino If the inoperable control rod is immovable or untrippable,perable. the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the famovable or untrippable control rod (s); and
= S R 3. t. t. t
- b. .At least once per 24 hours by consideration of the following factors:
- 1) Reactor Coolant System boron concentration,
- 2) Control rod position,
.3)
- Reactor Coolant System everage temperature.
- 4) ~ Fuel burnup based on gross thermal energy generation. *
- 5) . Xenon concentration, and
- 6) Samarium concentration.
I e_ *
/ w STS 3/4 1-3 i .
REACTIVITY CONTROL SYSTEMS l MODERATOR TEMPERATURE COEFFICIENT l LIMITING CONDITION FOR OPERATION _ L c.o b. V.L 3.1.1.3 The moderator temperature coefficient (MTC) shall be:
- a. Less positive than [0] Ak/k/'F for the all rods withdrawn, beginning j ef cycle life (BOL), hot zero THERMAL POWER condition; and
- b. Less negative than -[3.9) x 10 4 Ak/k/'F for the all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.
APPLICABILITY: Specification 3.1.1.3a. - 00 DES 1 and 2* only**. Specification 3.1.1.3b. - NDDES 1, 2, and 3,only**. { ACTION: i
- a. With the MTC more positive than the limit of Specification 3.1.1.3a. I above, operation in MODES 1 and 2 may proceed provided:
- 68"N W A .
- 1. Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 Ak/k/'F within 24 hours or be in HOT STAND 5Y within the next 6 hours.
These withdrawal limits shall be in addition to the insertion [\ limits of Specification Mw 3.1.3.6; Leo 5.t.L h 3
- 2. .The A,tdsol control rods are main within the withdrawal limits p p W' tained established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition; and N C6ss-Re t=S a wet S. S. U LO
- 3. A Special Report is prepared and submitted to the. Commission, pursuant to Specification 6.9.2, within 10 days, describing the value of the measured NTC, the interim contre) rod withdrawal limits, and the predicted everage core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
~ cousir1oa .2 -
- b. With'the NTC more neptive than the limit of Specification 3.1.1.3b. ,
above, be in HDT SHU"DOWN within 12 hours.
--* h P Pt i cui 'it7
*With Kpf greater than or equal to 1.
C*See Special Test Exceptions Specificat' ion 3.10.3. C* css - RE FR AEN CE J. l . I ts . *
/ w STS 3/4 1-4
SURVEILLANCE REQllIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as foll.ows:
- S6 3.f4.1
- a. The MTC shall be measured and compared to the BOL limit of Specifi-cation 3.1.1.3a. , abeve, prior to initial operation above 5% of RATED THERMAL POWER, after each fuer loading; and
- D e 3 1. L.3
- b. The MTC shall be measured at any THERMAL POWER and compared to
-{3.0) x 10 4 Ak/k/*F (all rods withdrawn, RATED THERMAL POWER condition) within 7 EfPD after reaching an equilibrium boron concen-tration of 300 ppm. In the event this comparison indicates the 1TC is more negative than -[3.0] x 10 4 Ak/k/*F, the MTC shall be remeasured, and compared to the EOL MTC limit of Specification 3.1.1.3b. , at least once per 14 EFPD during the remainder of the fuel cycle. ~
" SR 3.1.E.L e
a e a e G
/W STS 3/4 1-5 .
3.3 bdw Cw%1 Sp+cm REACTIVITY CONTROL SYSTEMS
- S.3 2 iO~MINIMUMTEMPERATUREFORCRITICALITY -
LIMITING CONDITION FOR OPERATION _ LC4 S.3.2 3.1.1.4 shall be greater than or equal to [5413'F.The Reactor Coolant System lowest op APPLICABILITY: MODES 1 and 2* **. ACTION:
~ vn ihin A With a feactor Coolant 5ystem operating loop temper
[541)*F, restore 7,,, to within its limit within'15 minutes or be in NOT l.STANDBYwithinthenext15 minutes. . SURVEILLANCE REQUIREMENTS SR 3.3.e. I
,_4.1.1.4 .
be greater than or equal to [541]'F:The Reactor Coolant System temperature (T"V
- a. Within 15 minutes prior to achieving reactor criticality. and , .
- b. At least once per 30 minutes when the reactor is critical and the I Reactor Coolant System T,yg is less than [551)*F with the T,yg-T,,y -
L Deviation Alarm not reset. e
\
h ff tLOn\iYy .3. 3. 2. [ *With K rester than or equal to 1.
=C*See Cras
Spec Penntes .s.3.2 ' l - Test Exceptions Specification 3.10.3.
. W S15 3/4 1-6
-O
Reh w %L.c h A N A}zcA & No rs L . REACTIVITY CONTROL SYSTEMS
~'
3/4.1.2 BORATION SYSTEMS FLOW PATH - SHUTDOWN ' LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source:
- a. A flow path from the Boric Acid Storage System via either a boric acid transfer pump or a gravity feed connection and a charging pump to the Reactor Coolant System if the Boric Acid Storage Systes in Specification [3.1.2.5a.] is OPERABLE, or
- b. The flow path from the refueling water storage tank via a charging-pump to the Reactor Coolant System if the refueling water storage tank in Specification [3.1.2.5b.) is OPERABLE.
APPLICABILITY: MODES 5 and 6. ACTION: With none of the above flow paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALT. RATIONS or positive reactivity changes. SURVEILLANCE REQUIREMENTS l 4.1.2.1 At least one of the above required f1w paths shall be' demonstrated OPERABLE: l
- a. At least once per 7 days by verifying that the temperature (of the l
. heat traced portion) of the flow path is greater then.or equal to
'(65)*F when a flow path from the boric ac< d tanks is .used, and
- b. At least once'per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its c^orrect '
position. V y STS 3/4 1-7 .
REACTIVITY CONTROL SYSTEMS M Md M. pe M 4, FLOW PATHS - OPERATING j U . 1 LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two* of the following three boron injection flow paths shall i be OPERABLE:
- a. The flow path from the Boric Acid Storage System via a boric acid ~ ;
4 transfer pump and a charging pump to the Reactor Coolant System (RCS),and b. Two flow paths from the refueling water storage tank via charging' pumps to the RCS. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: With only one of the above required boron injection flow paths to the RCS OPERABLE, restore at least two boron injection flow pa'.hs to the RCS to OPERABLE stsus within 72 hours or be in at least NOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1% Ak/k at 200*F within the next 6 hours; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within tne next 30 hours. '1 O . SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE: a. At least once per 7 days by verifying that the temperature (of the heat traced portion) of the flow path from the boric acid tanks is greater than or equal to [65)*F when it is'a required water source; b. At least once per 31 days by verifying that'ench valva (manual,
.. power operated, or automatic) in the flow path that is not locked.
. sealed, or.otherwise secured in position is in its correct position; c.
At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a _ test signal; and d. At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a. delivers at Least _ gpa to the RCS. 00nly one boron injection flow path is required to be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to [275]'F. -
/ySTS 3/4 1-8
. RdoW .ma.iA Aa .p p r> ore .d. .
REACTIVITY CONTROL SYSTEMS i CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 1 3.1.2.3 One charging pump in the' boron injection flow path required by Specification [3.1.2.1] shall be OPERABLE and capable of being powered from 1 an OPERABLE emergency power source. APPLICABILITY: MODES ~5 and 6. 1 ACTION: i l With no charging pump OPERABLE or capable'of being powered from an OPERABLE j emergency power source, suspend all operations involving CORE ALTERATIONS or i positive reactivity changes. l SURVEILLANCE R' REQUIREMENTS 4.1.2.3.1 The above req'iired charging pump shall be constrated DPERABLE by verifying, on recirculation flow, that a differential pressure across the pump of greater than or equal to psid is developed when testen' pursuant to-Specification 4.0.5. i 4.1.2.3.2 All charging pumps, excluding the above required OPERABLE pump, shall be demonstrated inoperable at least once per 31 days, except when the ; reactor vessel head is removed, by verifying that the actor circuit breakers ' are secured in the open position. O = S
/ W STS 3/4 1-9
-,. 9 4 02D A d x A A L. p e w ere L . l REACTIVITY CONTROL SYSTEMS ,
CHARGING PUMPS - OPERATING i-LIMITIN3 CONDITION FOR OPERATION l 3.1.2.4 At least two* charging pumps shall be OPERABLE. - APPLICABILITY: MODES 1, 2, 3, and 4. - i ACTION: . With only one charging pump OPERABLE, restore at lea'st two charging pumps to OPERABLE status within 72 hours or be in at least NOT STANDBY and borated to a 4 SHUTDOWN MARGIN equivalent to at least 2% Ak/k at 200'F within the.next i 6 hours; restore at least two charging pumps to OPERABLE status within the next-7 days or be in COLD SHUTDOWN within the next 30 hours. ! d
. i SURVEILLANCE REQUIREMENTS
( 4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE by verifying, on recirculation flow, that a differential pressure across each i pump of greater than or equal to psid is developed when tested pursuant to Specification 4.0.5. j 4.1.2.4.2 All charging pumps, except the above allowed OPERABLE pump, shall. I be demonstrated inoperable at least once per 31 days whenever the temperature of one or more of the Reactor Coolant System (RCS) cold legs is less than or. equal to [275)*F by verifying that the motor circuit breakers are secured in the open position. I
*A maximum of one centrifugal charging pump shall he SPERABLE whenever the
!{
j temperature of one or more of the RCS cold legs is lass than er equal to [275]'F. e y W STS 3/4 1-10
n ?. doc 4J .o&& .kaL. kyu & u-re A . REACTIVITY CONTROL SYSTEMS BORATED WATER 5011RCE - SHUTDOWN LIMITING CONDITION FOR OPERATION ( 3.1.2.5- As a minimum, one of the following borated water sources shall be j OPERABLE: 1
- a. A Boric Acid Storage System with:
- 1) A minimum contained borated water volume of gallons,
- 2) A boron concentration between [70003 ppe and [8000] ppe, and
- 3) A minimum solution temperature of [653*F. '
- b. The ref.ueling water storage tank (RWST) with:
- 1) A minimum contained borated water volume of gallons, !
- 2) A boron concentration,between [20003 ppe and [2200] ppe, and
- 3) A minimum solution temperature of [353'F. j j APPLICABILITY: MODES 5 and 6.
1 ACTION: With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity thanges. - SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required borated water source shall be i$ demonstrated OPERABLE:
- a. At least once per 7 days by:
^
- 1) ' Verifying the boron concentration of the unter, !
- 2) Verifyin'g the contained borated water volume, and-
- 3) Verifying the boric acid storage tank solution temperature when it is the source of borated water.
- b. At least once per 24 hours by verifying the RW5T temperature when it is the source of borated water and the [outside) air temperature is less than [353*F. ..
O - v' W STS 3/4 1-11 '
e $4$c&tb- e,ako,4cle Ed. & ore 4.. REACTIVITY CONTROL SYSTEMS O BORATE 0 WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 1 3.1.2.6 As a sinimum, the following borated water source (s) shall be OPERABLE as required by Specification 3.1.2.2:
- a. A Boric Acid Storage System with: *
- 1) A minimum contained borated water volume of gallons,
- 2) A boron concentration between [7000) ppe and {8000) ppe, and
- 3) A minimum solution temperature of [653'F.
- b. The refueling water storage tank (RWST) with:
- 1) A minimum contained borated water volume of gallons,
- 2) A boron concentration between (2000) ppe and [2200] ppe,
- 3) A minimum solution temperature of [35)*F and y 4) ,
A maximum solution temperature of [100]'F. ~ ( , APPL 1CABILITY: MDDES 1, 2, 3, and 4. ACTION: a. With the Boric Acid Storage System inoperable and being used as i one of the above required borated water sources, restore the system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and borated to a SHUTDOWN MARGIN equivalent to at least 1% Ak/k at 200'F; restore the Soric Acid l Storage System to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours.
- b. With the RWST inoperable, restore the tank to OPERABLE status within 1 hour or be .in at'least HOT STANDBY within the maxt
~
6 hours and in COLD SHUTDOWN within the followine 30 hours. e
/ W STS 3/4 1-12
l . PhawLnka kd.sya y weL. REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPER&BLE:
- a. At least once per 7. days by:
- 1) Verifying the boron concentration in the water,
- 2) Verifying the contained borated water volume of the water source, and
- 3) . Verifying the Boric Acid Storage System solution temperature when it is the source of borated wat4r.
- b. At least once per 24 hours by verifying the RWST temperature when the [outside) air temperature is either less than [353*F or greater than [100]'F.
O - l 9 y ., O 9 e 9 e 9 8 9 e o V y STS 3/4 1-13
~
REACTIVITY CONTROL 3YSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES i GR P HEIGHT , - L ?tTING CONDITION FOR OPERATION
- LCo S.1.3 3.1.3.1 All full length shutdown and control rods shall be OPERABLE and positioned within 1 12 steps (indicated position) of their group step counter demand position. .
APPLICABILITY: MODES 1* and 2*.
~
ACTION: , coc3; ftcu 4
- a. With one or more full-length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 bour and be in HOT STANDBY within 6 hours.
4 constrica a
- b. With more than one full-length rod inoperable or aisalpid from
- the group step counter demand position by more than i 12 steps (indicated osition), be in HOT STANDBY within 6 hours.
=--*. cow D / 'od .B
- c. With one f 1-length rod trippable twt inoperable due to causes
- other than addressed by ACTION a., above, or misaligned from its group step counter demand height by more thtn i 12 steps (indicated position), POWER OPERATION may continue provided that
, (, within 1 hour: '
- 1. The rod is restored to OPERABLE status within the above alignment requirements, or -
- 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within t 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Figures [3.1-13 and [3.1-2]. The THERMAL POWER level shall be restricted pursuant to Specification
[3.1.3.63 during subsequer.t operation, or -
- 3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. 30WER DPERATIDM may then continue provided that: -
~'
a) t A reevaluation of each accident analysis of Table 3.1-1 is
- performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these. accidents
- remain valid for the duration of operation under these conditions; b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 !
is determined at least once per 12 hours; 4
*See Special Test Exceptions Specifications 3.10.2 and 3.10.3. *
+ ckes.S -M= fE Renes s 3. I,y l&l. L Y W STS 3/4 1-14 .
REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) ' A bullkos 3 - c) A power distribution map is obtained from the novabh inceredetectorsandF(Z)andFhareveriffedtobe q within their limits within 72 hours; and d) The THERMAL POWER 1evel is reduced to less than or equal to 75% of RATED THERMAL M WER within the next hour and within'the following 4 hours the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL PDWER. SURVEILLANCE REQUIREMENTS q $ R 3.1.3.1 4.1.3.1.1 The positian of each full-length rod shall be determined to be - within the group demand limit by verifying the individual rod positions at least once per 12 hours except during time intervals when the rod position-deviation monitor is inoperable, then verify the group positions at least once-Mr 4 hours. .
~
'3R.S.i..s..t.
- 4.1.3.1.2 Each full-length rsJ ret fully inserted in the core shall be
- detemined to be'0PERABL:1 by movement of at.1oast 10 steps in ary one direction at.least once per 31 days.
9 e
]
1 e M US 3/4 1-15
- > T M 3.l.S - 4.
_ TABLE 3.1-1 ..
/"
.i ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH ROD Rod Cluster Control Assembly Insertion Characteristics
, Rod Cluster Control Assembly Misalignment Loss of Reactor Coolant free Sm:11 Ruptured Pipes or from Cracks in .
Large Pipes Which Actuates the Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal at Full Power Major Reactor Coolant. System Pipe Ruptures (Less-of-Coolant Accident) Major Secondary Coolant System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) O O 9 6 9 .
- d O
O -
/ W STS 3/4 1-16 -
REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION
% LC o 3. L.lo 3.1.3.2 The Digital Rod Position Indication System and the Demand Position Indication System shall be OPERABLE and capable of determining the control rod positions within i 12 steps.
APPLICABILITY: MODES 1 and 2. - - ACTION:
- a. With a maximum of one digital rod position indicator per bank inoperable co snMt = u A
- 1. Determine the position of the nonindicating rod (s) indirectly by the movable incore detectors at least once per 8 hours and
-1mmediately after any motion of the nonindicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or
~ co n mou .s
~
- 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours.
- een; rica A s 4 canalrica s
- b. With a maximum of one demand position indicator per bank inoperable either:
a Cwairiou c-
- 1. Verify that all digital rod position indicators for the affected
. bank are OPERABLE and that the most withdrawn rod and the least withdrawn red of the bank are within a maximum of 12 steps of each other at least once per 8 hours, or 9
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours. SURVEILLANCE REQUIREMENTS , , ,
, $ R 3.1. t * . I: .-+ 6 C 3. t. S. t 4.1.3.2 Each digital rod position indicator shall be determined to be OPERABLE by verifying that the Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps at least once per 12 hours except during time intervals when the red position deviation monitor is inoperable, then compare the Demand Position Indication System and the Digital Rod Position Indication System at least once per 4 hours. .
t .
/ W STS 3/I F 17 -
REACTIVITY CONTROL SYSTEMS P OSITION INDICATION SYSTEM - SNUTDOWN JO . LIMITING CONDITION FOR OPERATION R.J.a W M Ac.4 L. @ 4u weTE.1. 3.1.3.3 One digital rod position indicator (excluding demand position. indication) shall be OPERAELE and capable of determining the control rod position within 112 steps for each shutdown or control rod not fully inserted. APPLICABILITY: MODES 3" **, 4* **, and 5* **. ACTION:
- With less than the above required position indicator (s) DPERABLE, immediately open the Reactor Trip System breakers.
~
SURVEILLANCE REQUIREMENTS
#R 3.1.lo.h 4.1.3.3 Each of the above required digital rod position indicator (s) shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 steps when axercised over the full-range of rod travel.
~
R Jo & M .ku.1 s y u % NOTE R. '
*With the Reactor Trip System breakers in the closed position.
C*See Special Test Exceptions specification 3.10.5. l . ' v .
/ y STS , 3/4 1-18'
1 REACTIVITY CONTROL' SYSTEMS-ROD DROP TIME s LIMITING CONDITION FOR OPERATION
* %. % )Q -n & &G.JCaL. & % MofE %.
3.1.3.4 The individual full-length (shutdown and control) rod 1troptime from the fully withdrawn position shall be less than or equal to [2.2) seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:
- a. T,,, greater than or equal to [541]'F and b.! All reactor coolant pumps operating.
APPLICABILITY: MODES 1 and 2. ACTION,:
- a. With the drop time of any full-length rod detemined to exceed.
the above limit, restore the rod drop time to within the above limit-prior to proceeding to MODE 1 or 2. .
- b. With the rod drop times within limits but detemined with n-1 reactor O coolant pumps operating, operation may proceed provided THERNAL POWER is restricted to either:
- 1. Less than or equal to [66N of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are open, or
- 2. Less ihan or equal to [76 N of RATED THEllMAL POWER when the reactor coolant stop valves in the nonoperating loop are closed.
SURVEILLANCE REQUIREMENTS e .
,61R 5.\.S.$ .
4.1.3.4 The rod drop time of full-length rods shall be demonstrated through asasurement prtor.to reactor criticality: ' s
- a. For all rods followino each removal of the reacter vessel head, sw o- a 4 C. kuk.. w & wore t.
- b. For specifically affected individual rods following ary maintenance on or modification to the Control Rod Drive System which could a,ffect the drop time of those specific rods, and , i
- c. At least once per 18 months. .
sn 5.t.1.3
- t/ W STS 3/4 1-19 .
i
. J REACTJVITY CONTROL SYSTEMS
- p SHUTOOWN ROD INSERTION LIMIT i
LIMITING CONDITION FOR OPERATION
+ t 6.e 3.1. 8+
3.1.3.5 All shutdown rods shall be fully withdrawn.- APPLICABILITY- MODES 1* and 2" **. - l ACTION:
; tou:z>l m u 4 '
With a maximum of one shutdown rod not fully withdrawn, except for surveillance ! testing pursuant tolSpecification [4.1.3.1.2),1within I hour either:
- a. Fully withdraw the rod, or ~
- b. Declare the rod to be inoperable and apply Specification
[3.1.3.1). i ( SURVEILLANCE REQUIREMENTS
-- $ R 3. t .9. I 4.1. 3. 5 Each shutdown rod shall be detemined to be fully withdrawn: }
a
- a. Within 15 minutes prior to withdrawal of any rods in Control Bank A, B, C, or D during an approach to reactor criticality, and
- b. At least once per 12 hours thereafter.
1 4 CR.oss - RE.re RemE S 3. l. *l J 3 I IL .
'See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
)
"R*With K,gf greater than or equal to 1. .
l
- A ffU chm Ur/ '~
l 4 i i ( , d W STS' 3/4 1-20 l ( -- _ _ _-_-_-_Q
REACTIVITY CONTROL SYSTEMS d% CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION
~
L c o 5.l.5 3.1.3.6 The control banks shall be limited in physical insertion as shown in Figures [3.?.-1] and [3.1-2]. APPLICABILITY: MODES 1* and 2* **. ACTION: With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant
- contrico A. .
to[ Specification [4.1.3.1.2): I _ 4egu duu n ,,m a. Restore the control banks to within the limits within 2 hours or
- b. Reduce THERMAL POWER within 2 hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the hank posi-tion using the above figures, or
~ ~
- c. Be in at least HDT STANDBY within 6 hours. *
- C.cAfDiTIO4 C Q SURVEILtf.CE REQUIREMENTS 7
-. S R 3. t. s. L -
4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours except durinn time intervals when the rod insertion limit monitor is inoperable, then var fy the individual rod positions at least once per 4 hours.
+ ca.33 - gere e.eares s 3. 11 a .5. $11,
~
l
~
*See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
l **With K,ff greater than or equal to 1. !
- urLiedeJU ry '
i
~
d W STS 3/4 1-21
._ . , a.
- x ; ---- -
I E vi wcay pp .a Ai.s i+~, . FIGURE 3.1-1 ROD BANK INSERTION LIMITS YERSUS *(HERMAL POWER . FOUR LOOP OPERATION 3
/ W STS' 3/4 1-22
-1 J
j
- 1 1
l
. 1 q
i
~
. 3dend., p . p t::Mp-,_ Lee b t.f' it% ,u FIGURE 3.1-2
( ROI! BANK INSERTION LIMITS VERSUS' THERMAL POWER THREE LOOP OPERATION .
~
l
/ y.5TS 3/4 1-23
~ LC.o S. L.8 ( k , -
3/4.2 POWER DISTRIBUTION LIMITS i 3/4.2.1 AXIAL FLUX DIFFERENCE
, a I
' LIMITING CONDITION FOR OPERATION
- 3.2.1 The indicated AXIAL FLUX DIFT ?ENCE (AFD) shall be maintained within the following target band (flux difference units) about the target flux difference:
, s. t 5% for. core average accumulated burnup of less than er equal to ;
3000 MWD /MTU; and J
- b. + 3%, -12% for core average accumule.ted burnup of greater than 3000 t.co 3.t.b. MWD /MTU.
. Leo S.t.8.6 i The indicated AFD may deviate outside the above r; quired target band at greater than or equal to 50% but less than 90% of RATED THERMAL POWER provided the indi-cated AFD is .within the Acceptable Operation Limits of Figure 3.2-1 and the cumu- i s lative penalty deviation time does not exceed I hour .during the previous 24 hours.
, t.co s. s. s c-The indicated AFD may deviate outside the above required target band at greater !
than 15% but less than $0% of MTED THERMAL POWER provided the cumulative ' penalty deviation time does not exceed I hour during the previous 24 hours. - APPLICABILITY: MODE 1, above 15% of RATED THERMAL POWER.* l ACTION,: . 4 k a. With the indicated AFD outside of the above required target band and
~
with THERMAL POWER greater than or equal to 90% of RATED THERMAL ~ POWER, within 15 minutes either: - j
- 1. Restore the indicated AFD to within the target band limits, or !
- 2. Reduce THERMAL POWER to less than 90% of RATED-THERMAL POWER.
~ cow:pi rie.t D
- b. Etth the indicated AFD outside of the above required target band for more than I hour of cumulative penalty deviation time during the previous 24 hours or outside the Acceptable Operation Limits of Figure 3.2-1 and with THERMAL POWER less than 95 but equal to or greater than 50% of RATED THERMAL POWER:
- 1. Reduce THERMAL POWER te less than 55 of RATED THERMAL ' POWER within 30 minutes, and -
hs -ne rtunut 2. Reduce the Power Range Neutron Flux - High Trip ** Setpoints to
- 6. i.n less than or. equal 1o,55% of RATED THERMAL POWER within the next g _
4 hours. _xn% a Special Test Fxceptions Specification 3.10.2. Surveillance testing of the Power Range Neutron Flux Channels may be perfomed f9 pursuant to Specification 4.3.1.1 provided the indicated AFD is maintained within the Acceptable op'eration Limits of Figure 3.2-1. A total of 36 hours operation 5 may be accumulated with the AFD outside of the above required target band during testing without penalty deviation. !
-* nefLicemb iTY worn s/ w STS 3/4 2-1 .
. _ s ..
i i I
-POWER DISTRIBUTION LIM.(S- .
4 LIMITING CONDITION FOR OPERATION ACTION (Continued) . g 3, ,, g g g' g I
- c. With the indicated AFD outside of the above required target band'for more than 1 hour of cumulative penalty deviation time during the previous 24 hours and with THERMAL PDWER 1ess than 50% Let greater ,
than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be I increased equal to or ' greater than 50% of RATED THERMAL POWER until the indicated AFD is within the above required target band. SURVEILLANCE REQUIREMENTS I I
.4.2.1.1 The indicated AFD shall be detemined to'be within its limits during i l'
POWER OPERATION above 15% of RATED THERMAL POWER by _. $ u .t.s.1
- a. !
Monitoring the indicated AFD for each OPERABLE excore channel:-
, 1) At least once per 7 days when the AFD Monitor Alam is OPERABLE, and . , g pgs te, 3.te A A 3 l
- 2) At least once per hour for the first 24 hours after restoring i the AFD Monitor Alam to OPERABLE status. 1
- b. Monitori'ngafdloggingtheindicatedAFDforeachOPERABLEexcore I g channel at least once per hour for the first 24 hours and at least !
once per 30 minutes thereafter, when the AFD Monitor Alare is ; inoperable. The lo2ged values of the indicated AFD shall be assumed ' to exist during the interval preceding each logging.- !
- No 7 5 L L C o J.J.B r .
. i 4.2.1.2 The indicated AFD shall be considered outside of its target band when l two or more OPERABLE excore channels are indicating the AFD to be outside the-Jarget band. Penalty deviation outside of the above r y ired target band shall be accumu' lated on a time basis of: .
NOTE i L eo L t. 8 6.
- a. One minute penalty deviation for each I ainute of POWER OPERATION outside of the target band at THERMAL POWER 1evels. equal to or above '
50% of RATED THERM one-half une aminute su POWER, and L.co penalty so.AL i
- b. deviation for each 1 minute'ef POWER OPERATION i outside of the target band at THERNAL POWER 1evels between 15% and 50% of RATED THERMAL POWER.
, d c 3.t.s X 4.2.1.3 The target flux difference of each OPERABLE excere channe) shall be determined by measurement at least once per 92 Effective Full Power Days.
The rovisions of Specification 4.0.4 are not applicable. .
._ $ g 3.1.5.3
- 4. 2.1. 4 The target flux difference shall be updated at least once per .
31 Effective Full Power Days by either determining the target flux difference pursuant to Specification 4.2.1.3 above or by linear interpolation between the most recently measured value and 0% at the end of the cycle life. The provi- ' siens of Specificatier. 4.0.4 are not applicable.. V W STS 3/4 2-2
(O 4 4
.]
DekhL y yk}~& Leo 3.1.8 (h) xin)$ FIGURE 3.2-1 (\ . AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER '
- l 9
C y sTs 3/4 2-3 :
POWER DISTRIBUTION LIMITS 3/4.2.2 HEATFLUXHOTCHANNELFACTOR-FK l LIMITING CONDITION '/OR OPERATION I L t.o a l. 6 L A ) 3.2.2 F Q(Z) shall be limited by the following relationships: _.>d4x 4 w P W- uco 3.i.c taj tu e . Fn (Z) $ [2.32) [K(2)) for P > 0.5 i P , Fn (Z) 5 {(4.64)) [K(Z)) for P 5 0.5 Where: P = THERMAL POWER , and RATED THiRMAL POWER K(Z) = the function obtained from Figure [3.2-23 for a given core height location. APPLICABILITY: MODE 1. ACTION: With Fq (2) exceeding its limit:
- a. Comply with either of the following ACTIONS:
.- cons 1 rtou A ( h.s , A.L., A. y )
- 2. l Reduce THERMAL POWER at least 2% for each 2% F q (Z) exceeds I
the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours; POWER OPERATION may proceed.for up to a total of 72 hours; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 2% for each 1% 9F (Z) exceeds the limit, or
, 3 14t. A . W , e h W Leo b.t. 6 (A) 4 L 3
- 2. Reduce THERMAL POWER as necessary to meet the limits of Specification [3.2.6) using the Axial Power Distribution Monitoring Systems (APDMS) with the latest incore map and updated 1. f,ApDMS plants only) '
l 73;.c4A.L. p wWPern Lco 314(4) 4 4
. b.- Identify and correh tfw cause of the out-of-limit condition ;
prior to increasing THERMAL POWER above the mduced limit re-Quired by ACTION a., above;' THERMAL' POWER may then be increased provided Fq(Z) is demonstra".ed through incere mapping to be within its limit. '
~ con 2> (Tim 4 (4 5) .
/ y STS 3/4 2-4
. . .\
.i
)
l;
~
l
't
~
34AL p pA'A Leo'3.l.6(A) M d. M I FIGURE 3.2-2 -
, K(Z) - NORMALIZED F q (Z) AS A FUNCTION OF: CDRE. HEIGHT.
V WfSTS 3/4 2-5 ,
POWEk 015TRIBUTION LIMITS f SURVEILLANCE RE001REMENTS qu Whw NM 4.2.2.1 The provisions of Specification 4.0.4 are not applicable. L ., s g 3. 1 6 1. 4.2.2.2 F,y
~
$ R, 3. n . 6NeTE
. .tshall
- 4. be evaluated to qdetermine if F (Z) is within.its limit by:
- a. Using the movable incere detectors to obtain a power distribution map at any THERMAL POWER greater than SE of RATED VMERMAL POWER,
; .5 s 6.1. 6.L wee 3
- b. Increasing the measured F component pf the power distribution map yy by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties,
- c. Comparing the F 9 computed (F,C) , obtained in Specification 4.2.2.2b. ,
"D "'d i e 3.i.c.t dove H
- 1) The F,y limits for RATED THERMAL POWER (F ) for the appropriate measured core planes given in Specification 4.2.2.2e. and f.,
be10w. and x sg. s.t.s. L wars 1
- 2) The relationship: % w p .
e ., t eo 3. g. 6 (4;.eu a4 Fxyl=FRTP xy [1+0.2(1-P)), " # #' 3"' ' " Y ( Where F l is the limit for fractional THERMAL POWER operation - express as a function of F,RTP and P is the fraction of RATED THERMAL POWER at which F,y was measured. - d. Remeasuring F,y according to the following schedule:
- 1) When F,C is greater than the F,RTP limit for the appropriate .
measured core plane but less than the F l relationship, additional power distribution maps shall be taken dF C compared to F,RTP and F,y either: , a) Ythin 24 hours after exceeding by 205 of RATED ~THEWEL POWER or greater, the THERMAL POWER at which F C ,,,j,,g determined, or -54 3. I. 6 L acre 6 b) At least once per 31 Effective Full Power Days (EFPD), l i whichever occurs first. , i I
- SK 3. l. 6. L i
/ W STS 3/4 2-6
Docket No. 50-445 August 14, 1987 POWE9 DISTRIBUTION LIMITS
$ SURVEILLANCE REQUIREMENTS (Continued)
- 2) en the F C is less than or equal to the F limit for the 1 appropriate seasured core plane, additional power distribution' maps shall be taken and F C compared to F and F et least ,
once per 31 EFPD.Atw 4u. p AN Lee 3.Lc (4)4h A/, "
. a. The F,y limits for RATED THEBEL POWER ( , )'shall be provided for all core planes containing Bank *D" control rods and all unrodded core planes in a Radial Peaking Factor Limit Soport per Specifica-tion 6.9.1.6; S r J.J. C.L N o rt b
- f. The F,y-limits of Specification 4.2.2.2e., above, are not applicable ;
in the following core planes regions as esasured in perce.it of. core height from the bottom of the fuel: - -
- 1) Lower core region from 0 to 155, inclusive,.
- 2) Upper core region from 85 to 2005, faciusive.
. -l
- 3) Grid plane regions at 17.8 2 25, 32.1
- 25, 46.4
- 5 , 60.6 t 5 ,
and 74.9 1 25, inclusive, and 1 i 5- l
- 4) Core plane' regions within 1 25 of core heig"ht (a 2'.88 inches) '
about the bank demand position of the Bank D" control rods. C
= SR.s.l.C.L NorE $~
g'. With F exceeding F : , ge, g g,g (g) jy p g ,,,, g ,
- 1) The F q (Z) limit shall be reduced at least 3 for each 35 F, {
exceeds F,y, and (for plants with Fg(2) less than 2.32 and using APDMS) , l
. 2) The effects of .F, en Fg (Z) shall be evaluated to detettine if 1 Fq (Z) is within its limits. ,
~4.2.1.3 When g,F (Z) is enesured for other than F, ,.Wastions, an overall esasured Fg (Z) shall be obtained from n' power die lbution map and increased j by E to account for manufacturing talerances had further lacreased by 55 to account for sensurement uncertainty.
=$A3.I.C.I =~4 Se o. l. C. I "*TE O
V COWW6CHE PEAK - UNIT 1 3/4 2-7
Docket No. u0-445 August 14, 1987* POWER DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE MDT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.0 5ee nv4 tt 3.f.3 The combination of indicated Reactor Coolant Systae (RCS) total flow L rate and R shall be maintained within the region of allowable operation shown en Figure 3.t-3 for four Ieop operation. . Where: .
- =- u, u. . . L u. . . ,n -
THEIMAL MWER , innd b* P= RATED TNUIMA.. POWER
- c. Fh = Measured values of F" g ebtained by using the aevable incore eletectors to otrtain a power distribution esp. The esasured values of F"y shall be used to calculate R since Figure 3.2-3 includes per.alties for undetected feedwater wenturf fouling of
[0.135 and for measurement uncertalaties of [2.235 for flew and 4% for incere esasurement of F" g . - APPLICABILITY: MODE 1. i ACTION: . With the combination of RCS total flew rate and 4 outside the region af acceptable operation shown on Figure 3.2-3: -
- a. 4Hthin 2 hours either: .
- 1. Restore the combination of RCS total flou vote and R to within the above limits, or
- 2. Reduce THERMAL POWER ta less than SIE of RRTED TIESt4L POWER I
..and toduce the Power Range llestron Fleet - #1 THp Setpoint to
-less than er equal to SEE of AATED TIESIAL within the east 4 hours.
e CDPMCHE PEAK - UNIT 1 3/4 2-8
, q u
- ]
i 4 1 l
.j
'I i
W i l 1 1 i
. , .. . 'j FIGURE 3.2-3 !
RCS TOTAL FLOW RATE VERSUS R - FOUR LOOPS IN OPERATIO i I
- CDMANCHE PEAK - UNIT 1 3/4 2.g
'6
__________.m_____. __.__m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .
l Docket Ilo. 50 445 August 14. 1987 POWER DISTRIBUTION LIMITS
$ e_ e td =h ( (
- LIMITING CONDITION FOR OP'AATION
'~ '
ACTION (Continued) !
- b. Within 24 hours of initially being_sutside the above limits, verify !
through incore flux espping and sc5 total flow rate comparison that ! the combination of R and RCS total flow reta are restored to within i the above limits.'or reduce THEML POWER to less than SE of RATED l THERMAL POWER,withis the next 2 hours.
- c. 3dentify and correct the cause of the out-of-limit condition prior ;
to increasing THEIMAL POWER above the reduced THERMAL POWER limit i required by ACTION a.2. and/or b., above; subsequent POWER OPERATION l may proceed provided that the combinatten of A and indicated RCS l total flow rate are demonstrated, through incere flux espping and RCS total flow rata esaparisong to be within the region of acceptable aperation shown en Figure 3.1-3 prior to exceeding the following THERNAL F0WER 1evels:
- 1. A meninal 50K of BATED TIEstAL 90WER, .
l
- 2. A moninal 75E of RATED THENL POWER, a'nd
- 3. Within 24 hours of attaining greater than er equal to 955 of ,
-RATED THERMAL POWER. !
. 1 h SURVEILLAWtf REQUIREMENTS i 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.
4.2.3.2 The combination of indicated RCS total t* low rete and R shall he deter-eined to be within the region of acceptable operation of Figure 3.2-3: l
- a. Prior to operation above 75K of RATED TIENIAL PdWER after each fuel ;
leading, and
- 6. At least once per 31 Effective Full power Days.
4.1.3.3 The indicated RCs total fisw rets shall be %erffled to be within the ; regten of acceptable operstfun of Figure 3.2 3 et least once per 32 hours ehen ! the most recently obtained value of R. ettaland per Speciffurtion 4.L3.2. is l assumed to exist. , l 4.1.3.4 The RCS total flew reta indicators shall be si4jected to a OIANNEL, l CALIBRATION at least once per 38 months. The measurement instrumentation shall be calibrated within 7 days prior.ta the performance of the calorimetric flow measurement.
~
4.2.3.5 The RCs total flow rate shall be determined by precision heat balance esasurement at least once per 18 months. ' , CDMANCHE PEAK - UNIT 1 3/4 2-10 I
f.'ctet No. 50'-445 POWER DISTRIBUTION LIMITS b lust 14, 1987 3 /4. 2. 4 OUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION - LCO 3. L . S See tJM ' t ?_. 3.2.4 The QUADRANT POWER TILT RATIO shall met exceed L02. APPLICABILITY: - MODE 1, above 50K of RATD TIEMAL POWER *. ACTION:
- a. tiith the QUADRANT POWER TILT RATIO deterstaed to exceed 1.02 but less than er equal to 1.09:
- 1. Caleviste the QUADRANT POWER TILT RATIO at least once per hour until either: .
a) The QUADRANT POWER TILT RATIO is Teduced to within its limit, or b) THERMAL POWER is reduced to less than SOE af RATD THERMAL POWER.
- 2. Within 2 hours either:
(V - a) Reduce the QUAERANT POWER TILT RATIO to within its limit, or i b) Reduce THERMAL POWER at least 35 from RATD THERMAL p0WER for each 15 of indicated QUADRANT POWER TILT RATIO in ! excess of 1 and similarly reduce the Power Range Neutron d Flux-High Trip 5etpoints within the maxt 4 hours. l
- 3. Verify that the QUADRANT POWER TILT RATIO is within its lieit within 24 hours after exceeding the Itait er reduce THERMAL POWER to less than 50E of RATED THERMAL POWER within the next l 2 hours and reduce the Power Range Neutron Flux-Migh Trip ;
Setpoints to less than er equal to SAE of RATD THERMAL POWER ' within the next 4 lysurs; and , j
- 4. - Identify and correct the conse. of the out-of-limit condition !
prior to increasing THERMAL POWER; semequent POWER OPERATION ! above SOE of RATE THERMAL POWER mRy proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least ence per hour for 32 hours or until verified acceptable at 95% or greater RATD TEMAL POWER.
. *See Special Test Exceptions Specification 3.10.2.
A COMANCHE PEAK - UNIT 1 3/4 2-11
~
Docket No. 50 445 POWER DISTRIBtrTION LIMITS August 14, 1987 LIMITING CONDITION FOR OPERATION LCC 31 A A hj .% gg ACTION (Continued)
- b. With the QUADRANT POWER TILT RATIO determined to exceed 1.09 oue to misalignment of either a shutdown or control red: ,
- 1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:
a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER 4s reduced to less'than 50K of RATED THERMAL POWER.
- 2. Aeduce THERMAL POWER at least M from RATED THERMAL POWER for.
each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1, within 30 minutes;
- 3. Verify that the QUADRANT POWER TILT RATIC is within its limit within 2 hours after exceeding _the limit er reduce THERNAL' POWER to less than 50% of RATF.D THERMAL POWER within the next 2 hours and, reduce the Power Range Neutron Flux-High Trip 5etpoints to less than er equal to 555 of RATED THERMAL POWER 4 4.
within the next 4 hours; and Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION
. above 50% of RATED THERMAL POWER any proceed provided that the.
QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours or until verified acceptable at 95% or. greater RATED THERMAL POWER.
- c. With the QUADRANT POWER TILT RATIO determined to exceed 1.09 det to causes other than the misalignment of either a shutdown er control rod:
- 1. Calculate the gunDRANT POWER T11.7 BAT 30 at laest once per hour until either: ,
a) The QUADRANT POWER TILT RATIO is reduced to within its llett, or , b) THERNAL' POWER is reduced to less then 50K of RATED THERMAL I POWER. . . 1 e
Docket No. 90-4 5 I" ' b l
. POWER DISTRIBtrTION LIMITS LIMITING CONDITION FOR OPERATION LC O 3 . ( . '1 5ee ' No:Q JL .,
ACTION (Continued)
- 2. Reduce THERMAL POWER to less than SOE of RATED THERMAL POWER ,
within 2 hours and reduce the Power Aante Neutron Flux-High Trip 5etpoints te less than er equal to SEE of RA*.ID THERMAL POWER within the next 4 hours; and
- 3. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above SOE of RATED THERMAL POWER any proceed provided that the-QUADRANT POWER TILT RATIC is verified withiri its limit at least once per hour for 12 hours or until verified at 95E or greater RATED THERMAL POWER.
- d. The provisions of Specification 3.5.4 are mot applicable.
SURVEILLANCE REQUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be datamined to be within the
, limit above 50% of RATED THERMAL POWER by: . .
\ a. Caleviating the ratio at least once per 7 days when the alars is OPERABLE, and
- b. Calculating the ratio operation when the alaat least rs is once per 12 hours during staa@-state inoperable.
4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incere detectors to confim that the normalized t,yanetric power distribution, obtained from tuo sets of four symmetric thimble locations or full-core flux emp, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 22 hours. i n . COMANCHE PEAK - UNIT 1 3/4 2-13
..m-
uen.t m. so-uS _3.s Ruuhr Cwan s dem
! 'O PA ETE LIMITING CONDITION FOR OPERATI0i! ,
i m LCO 3.3.1 - 3.2.5 The following DNB-related parameters shall be maintained within the limits shown on Table 3.2-1:
- a. Reactor Coolant Systaa T,,,, and 3
- b. Pressurizer Pressure.
{ . APPLICABILITY: $WDE 1. ACTION: 1h
- Lorib. r . lot $ b b1t00 With any of the above parameters (exceeding its limit, nstere the parameter to within its limit within 2 hours or reduce THERMAL POWER to less than 5 of RATED THERMAL POWER within the next 4 hours.
SURVEILLANCE REQUIREM M S Q~ SR 3.3,l.) thrx3 h SR 3.s. l.3 4.2.5 Each of the parameterr of Table 3.2-1 shall be verified to be within its limits at least once per 12 hours. - . 9 I
- e COMANCHE PEAK - UNIT 1 3(42-14
,L Docket F3. 50-445 '
. August kJ., 1987 a,g %- LCO S.3,i
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/ 3/4.3 INSTRUMENTATION s 3. 2. . ]
3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION Aco 3.2.1 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2. APPLICABILITY: As shown in Table 3.3-1. ACTION: 3 7.1-/ As shown in Table 3.3-1. 3.2.1-l SURVEILLkNCEREQUIREMENTS
-,JR S .t./, / -/4 y J R 3. 7.1. 2 2.
4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic *shall be demonstrated OPERA 8LE by the performance of l.' the Reactor Trip System Instrumentation Surveillance Requirements specified in ( Table 4.3-1. 4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least onc.e per 18 months. Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months whare N is the total number of redundant channels in a specific Reactor trip function as shown in the _ Total No. of Channels" column of Table 3.3-1. L
/COMANCHEPEAK-UNIT 1 3/4 3-1
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/COMANCHEPEAK-UNIT 1 3/4 3-5
-1 l
[ TABLE 3. 3-1 (Continued) 3,2,1-/ 1 A TABLE NOTATIONS "When the Reactor Trip System' breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal. l 7=n Uh5.16D3e d 'L g g3,. g 337 9 ( % s,3L Q ,7,h t ,__,,,,, ,___ ,,, i t
. ........~...
#The provisions of Specification 3.0.4 are not applicable.
MBelow the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
##8elow the P-10 (Low Setpoint Power Range Neutron Flux Inter 1cck).Setpoint.
CoyDI7 sod ACTION STATEMENTS CotDilictU ACTION 1 - With the number of OPERABLE channels one less than the Minimum B Channels OPERABLE requirement, restore the inoperable channel ( to OPERABLE status within 48 hours or be in HOT STAND 8Y within the next 6 hours. i M ot7~oon) f ACTION 2 - With the number of OPERA 8LE channels one less than the Total g Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 1 hour,
- b. The Minimus Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours for surveillance testing of other channels per Specification 4.3.1.1, and
- c. Either, THERMAL POWER is restricted to less than or equal .
to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced ta,.less than or equal to { j [8535 of RATED THERMAL POWER within 4 hours;'or, the ; QUADRANT POWER TILT RATIO is monitored at least once per ; 12 hours per Specification 4.2.4.2. 1 I 1 s dOMANCHEPEAK-UNIT 1 3/4 3-6 l
i p TABLE 3.3-1 (Continued)3.2./-l k ACTION STATEMENTS (Continued) Co MooTooN
*~
Cedetttcr/ ACTION 3 - With the number of channels OPERABLE one less than the Minimum i Channels OPERABLE requirement and with the THERMAL POWER. level: l E a. Below the P-6 (Intennediate Range Neutron Flux Inter 1ch) Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6' a
.. Setpoint, and ,
j
- b. Above the P-6 (Intermediate Range Neutron Flux. Interlock)
F Setpoint but below 10% of RATED THERMAL POWER, restore ~ the -l inoperable channel to 0PERA8LE status prior to increasing l THERMAL POWER above 10% of RATED THERMAL POWER. Cavoined ACTION 4 - With the number of OPERA 8LE channels one less tnan the Minimum H Channels OPERABLE requirement, suspend all operations involving 1 positive reactivity changes. ! CcWM7uJ . . ACTION 5 - With the number of OPERABLE channels one less than the Minimum y Channels OPERABLE requirement, restore the inoperable chantiel -l to OPERABLE status within 48 hours.or open the Reactor Trip g . .Systes breakers, suspend all operations involving positive'
.- reactivity changes and verify Valves are closed and secured in position;within the next hour.
l%!ainoJ ACTION 6 - With the number of OPERA 8LE channels one less than the Toto . i g Number of Channels, STARTUP and/or POWER OPERATIDH may procahd ! q provided the following conditions are satisfied: l
- a. The inoperable channel is placed in the tripped condition within I hour, and , ,
J
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel any be bypassed for up to 2 hours for surveillance testing of other channels per Specification 4.3.1.1.
l%/oinor/ _
-ACTION L 7 - With the number of OPERABLE channels one less than the Total-M Number of Channels, STARTUP and/or POWER OPERATION may proce&d
..n___,____..,.u~-~ -- . ne em naemahm ,
i - R ~ T isst p 6 ided the inoperabie ch sne fis placed in the irI M J condition within 1 hour. (oMoities/ DELETED See Leo 3 td Id37ACAT'W T N @S ACTION 8 - With less than the Minimum Number of Channels OPERABLE, with f I hour determine b :t:: crt*-- ^' * % ter e ete ;: r'5:* 0 d y tr r:*-t e't ' ) that the interlock fu in 'its required state for.the existing plant condition, or apply Specification 3.0.3. \
~
NOMANCHEPEAK-bMIT1 3/4 3-7
l TABLE 3. 3-1 (Continued)3.2./+/ - ACTION STATEMENTS (Continued) Cecomea
~ {
DELETES $ce LCo 2.2.1 Twi tFi cATe nM *Ttem
- l7 ACTICM 9 - 91 : channe! :::: fated etth :n :::r:tfng Tee; 'n ;:r:ble, i
- tere the 'aesereble then e? te 0*E*ABLE et +": efth'- 2 5:urs er 5: ' :t !:::t "0T ST.^?SSY rith*- the n:nt 5 5: r:.-' -one channel :::erf:L-d =fth :n :;;r:tfe; 1::; :y 50 by;;;;;d-for.
up te 2 ^er : 'er ter;:f'! ne: *e-*'n; ;;r S;::f::tf:r t.2.1.1 . A bhYO-WiththenumberofOPERA8LE.channe'1sonelessthantheMinimum ! T Channels OPERA 8LE requirement, be in at least NOT STANDBY E within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE. fedDi&J ACTION 11 - With the nurber of OPERABLE channels one less than the Minimum 1 C Channels OPERABLE requirement, restore the inoperable channel. to OPERABLE status within 48 hours or open the Reactor. Trip System breakers within the next hour. 5CT!ON 12.,- N .N S:3, D : ca. . 0 '
$2.frMI'!:I: fnth: 'Tet:1 ""-':r
..... 4.. ...,.4.. --...u.a +6. 4--- ..w3.
Chann:!: cre ;!ered '- the trf;;:f ::: ftfen eith'- I heur. co^r0Grd . c ACTION 13 - With one of the diverse trip features (undervoltage or shunt E trip attachment) inoperable,: resto:1t it to OPERABLE status M within 48 hours or declare the breaker inoperable and apply ACTION 10. The breaker shall not be bypassed while'one of the diverse trip features is inoperable except for the time required for perforniing maintenance to restore the breaker to OPERABLE 1 status, j 4 N
./ COMANCHE PEAK - UNIT 1 -
3/4 3-8
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- W8 **"b 5 N b k' TABLE 4.3-1 (Continued) Y '1 A "
- 3' 2'l \
TABLE NOTATIONS fo s7f pfcg7/cN
.2~ te'th *
"When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.
"*Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint. j
***Below P-10 (Low Setpo1nt Power Range Neutron Flum Interlock) Setpoint. )
31 (1) If not performed in previ@ous f days. @ $ ! (2) Comparison of calorimetric to excere power indication above 15% of RATED j THERMAL POWER. Adjust excore channel gains consistant with calorimetric < power if absolute difference is greater than 25. The. provisions of @ Specification 4.0.4 are not applicable to entry into teDE 2 mr 2. (3) Single point comparison of incore to excore AXIAL FLUX ' DIFFERENCE-above 15% of RATED THERMAL POWER. Recalibrates if the absolute m difference is greater than or equal to 35. The provisions of W i Specification 4.0.4 are not applicable for entry into ICDE 2 or 1. 1 (4) Neutron detectors may be excluded.from CHAlWEL CALIBRATION.@ E"' kfET.9. .h*,.L.C0 h31.L.U$FLi'i.M"P R _...... a
._a --- . .'
Z Z ,.: Z ~ n.'I.; - 'en . c E z r i.;_ . r ' a .-"'_ . 1: --
s 1 .Z "~ ; E 2 .:_' U' k.' L .T,~:,::_'~ m z zi,,'Z "I_:"; k I ~ J-~"; .
" - " ' ' - ' ' ' " " ' ' ' - ' ' ~ ~
Z _,Z G. . '1i. _' "L. :. "I_'.!.'.J,?4 Z.._': LAR T_ Z. ',". g ___ (6) Incore - Excore Calibration, above 75X of RATED THEIMAL POWER. Theg provisions of Specification 4.0.4 are not applicable'for entry into MODE 2 or 1. (7) Each train shall be testad at least svary A2. days on a STAGGERED $ $ TEST BASIS. (8) With power greater than or equal to the Interlock Setpoint the required ANALOG. CHANNEL OPERATIONAL TEST shall consist of verifying that the @
, interlock is 1 required stata ' -t -- * * ' - --! --
ed *-- -tadow. . (9) Monthly surveillance in feDES '3*, 4*, and 5" shE11 also include E b
, verification that pomissives p-6 and P-10 are in their required state for existing plant conditions W ir::!'-- ef '" ;:x'::' e @
- , _-.- f ete- # 1.
Monthly surveillance shall in:1ude verification of the Baron Dilution Alare Setpoint of less than er equal to (an increase of twice the count rate within a 10-minute period). i
/COMANCHEPEAK-UNIT 1 3/4 3-14 l l
, I gm ,
i TABLE 4.3-1 (Continued) . TABLE NOTATIONS (Continued) l (10) Set;ointverificationisnotapplicable.@ i (11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the ' i OPERABILITY of the uncervoltage and shunt trip attachments of the Reactor ! Trip Breakers. @ j (12) At least once per 18 months during shutdown, verify that on a simulated ! l Boron Dilution Doubling test signal the normal CVCS discharge valves g 4 close and the centrifugal charging pumps suction valves from the RWST j open within 130] seconds. j ( (13) CHANNEL CALIBRATION shall include the RTD trypass loops flow rata.@ (14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify @ the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. T5: *2:t th:1' a!: ter4*y t M 3*EP^"ILI F cf the
-Bypas: Bre:Eertriprfreeft':).@
L(15) tecel eneal she- t-4; ;-<e- te 7 1 er4 t--e% - refe. or te pl e".t: that de not ar+"ete the shunt t-i; atterh = t Of the typ::: tr;;her; :n : n n=:? react:r tr#-': "-- te nrral cc-%;rv:lt:;: trip
'd:r breaker p' ired da territe_ h lJ
= = = =t4: ==e:r= ,1:; tr4; e -
l l c e i l i 1 1 I t CDMANCHE PEAK - UNIT 1 3/4 3-15 '
- _o
Socket No. 50-445 INSTRUMENTATION August 14, 1987
- 3. 2. Q.
( 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 4r0 3 Q. Q. 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Tab 1'e 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 c d !th "558=l! TI."5 :: drr- S Td? ?_ ?-5 lee Leo 2.a.a. J.J.2-/ 3,.t2,-/ WJTaf'iCATafd APPLICABILITY: As shown in Table 3.3-3. D* " 6 3,ub2-/ ACTION:
- beleted See L.CO3.2.2 "Jos d:scATete Tdem
- A.
- a. With :.- ESF.23 hetmtet en er Iate-19t6 T*f s Se+=a* =+ t-ip less
-sensery:tive than tha tele ska-a da tha T-f; Cataafat **1 e a but sere cense vative tM a t A= vel"= sh (a +ha A 11 ~=h 1 = V= 1 = r e ' '- - _
l ef Te!e 3.3 2,' edfert tM 9+ eiat ee riste-t "4+3 +M Trip h* efat - _vslee.
- b. With an ESFAS Instrumentation or Interlock Trip 5etpoint less conserva-tive than the value shown in the Allowable Value column of Table 3.3-4, either:
- 1. '~-..
1 EP, !$. .ck...,. g,ggy.,a,,.,2,,{ggpi.%wy ,3 M,. ,. ,.,. _. , ,_ _',
. . _ , . . . . . _ _ . . . . . _ _ . ~ . _ . . . . ..
Te:;ie 3. 2 ', =d detea-i-- withia M Mras thet Er tier 2.2-1 ger ::tisfied fr- tM eff*-+44 eM- r!, sa N - coa f
- 2. Declare the channel inop%TldrJerab e and' apply the applicable ACTION statement requirements of Table 3.3-3 until the channel is
, restored to OPERABl.E status with its Setpoint adjusted consistent with the Trip Setpoint value. .f J,J. -/ E';r tien 2.2-1 ?
- e . y ; rm m- :. Deleted $ce. CCo 3.a.a JosTif* stat ***J TAem 84 The ve!"- faa- Cel'_- Z =* TeSeM S-A ' -- t h= effeted eh:...;1, -
l " - The ":: = :: 7;:" v ! r (4- ;_ :xf_ r;--) ef n d ;r ;r f:r th:
. =<f ,+ g 6- - 1, E - Eith:r th: "e: r it " -we' M ('a -- w **=a) a' +ka s===aa
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- c. With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
3.1 2,-l k COMANCHE PEAK - UNIT 1 3/4 3-16
Booket Sio. 50-445-INSTRUMENTATION August 24, 1987
$ SURVEILLANCE REQUIREMENTS . - 6 6 3.2.2./ tir uy L E R 3. 2. 2. t L 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of .
theESFASInstrumentationSurveillanceRequirementsspecifiedinTable4.3-2.l 3.a. 3 - l 4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one train such that both trains are tested at-l 1 east once per 36 months and one channel per. function such that all channels are tested at least once per N times 18 months where Il is the total number of redundant channels in a specific ESFAS function as shown in the ' Total No. of Channels" column of Table 3.3-3. 3.2.;a 1 4 a 1 I il i
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Gooket No. 50-445 J.2.J / August 14,1987 TABLE 3.3-3 (Continued) ([-. TABLE NOTATIONS
."The paovisions of Specification 3.0.4 are not applicable.
#The (Safety Injection] logic for this trip function may be' blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.
**The [ Safety Injection] logic for this trip function say be blocked in this NODE below the P-12 (Low-Low T,,, Interlock) Setpoint.
***The channel (s) associated with the protective functions derived from the
. . out of service rasctor coolant loop shall be placed in the tripped mode.
*** Trip function automatically blocked above P-Il and any be blocked below P-11 when Safety Injection on low staan line pressura is not blocked.
CoM/7Ie/\/ ACTION STATEMDITS
- team.a -
ACTION 14 - With the number of OPERABLE channels one less than the Minimum C. Channels OPERABLE requirement, be in at least NOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing-per Specification 4.3.2.1, provided
. the other channel is OPERABLE. .
cwurd - ACTION 15 - With the number of OPERABLE channels one less than the Total D Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour. f*MoWd rA/M b Lee 2.n.2 lLarsanwJ h Eo 1 EupN .Le - w1th a enannel assoc 1 sten with an operating loop inoperable. restore the inoperable channel to OPERABLE status within 2 hours or be in at-least hitT STAISBY within the next 5 hours and in at least HDT SHLITDOWN within the following 5 hours. One channel associated with an operating loop any be bypassed for un t.a 2 wm far mm = *can == "ifie=Han 4.1. 2 L
. Csaoiraa ACTION 17 - With the number of OPERABLE channels one less than the Total F Number of Channels, operation may proceed provided the inoperable
-g channel is placed in the bypassed condition and the Minimum Channels OPERAELE requirement is set. One meditional channel any be bypassed for g to 2 hours for surveillance testing per Specification 4.3.2.1.
ACTION 18 - With less than the Minism Channels OPERABLE requirement. H oper M n may continue provided the containment purge supply and er.haust valves are maintained closed.
/ COMANCHE PEAK - UNIT 1 3/4 3-28 i
Socket No. 50-445 August 14, 1987 TABLE 3.3-3 (Continued)2, g ACTION STATEMENTS (Continued) Cowoind . l ACTION 19 - With the number of OPERABLE channels one less than the Minimum B Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours and in COLD .SHUTDOW within the following 30 hours. - 4,ang,g ACTION 20 - With the number of OPERABE channels one less than the Total D Number of Channels, STARTUP and/or POWER OPERATION may proceed E provided the following conditions .are satisfied:
- a. The inoperable channel is placed in the tripped condition
~
within 1 hour, and
- b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours for surveillance testing of other channels per Specification 4.3.2.1. .
ACTION 21 - With less.than the Minimum Number of Channels SPERABE, withig y 1 hour determine by rM -"stfe ef *M e55Sefe+" pe--f:8:D$e a- e-cSte v "Me) that the interlock is in its requiredLcQQA i state for the existing plant condition, or apply SpecificatNnyw, ,7 3.0.3.
+ 6darisa .
ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least NOT STANDBY 7 within 6 hours and in at least HOT SHUT 00WN within the following 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1 provided the ether channel is OPERABLE. - Coco,7.d ACTION 23 - With the number of OPERABLE channels one less than the Tetal Number of Channels, restore the insperable, channel to OPERABLE 1 status within 48 hours or be in at least NOT STANDBY within a 6 hours and in at least HDT SHUTDOW within the following l
- -6 hours. ;
MaeL 4 LCo %G.3 Se s Leo k.2.t % n n w To d AcupN 24 - With the numer of wrdABLE channels.ane less than the Tota'
~
Numer of Channels, restore the inoperable channel to OPERABLE i status within 48 hours or declare the associated valve inoperable l anst taka +ha ACTf0N r- ired by '---ffientian fl.7_1.111 hm A/='L l l%47W . . i ACTION 25 - W1th the number of OPERABLE channels one less'than the Minimum Channels OPERABLE requirement, be in at least HDT STAm8Y within K 6 hours; however, one channei may me bypassed for , to hours for surveillance testing per Specification 4.0.?.1 provided the other channel is OPERABLE. COMANCHE PEAK - UNIT 1 '3/4 3-29 1
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1 Booket tio. 50-445 1 August I4,1987 TABLE 3.3-4 (continued)ya,2 _ i TABLE NOTATIONS
" Time constants utilized in the lead-lag controller for Steam Line Pressure-Lew )
are T3 > [50] seconds and Tz 1 [5] seconds. CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these' values.
**fhe time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate-High is less than or equal to [50] seconds. CHANNEL CALIBRATION shall ensure that this time constant is adjusted to this value.
e 4 l
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^
[CONANCHE PEAK - UNIT 1 3/4 3-36
Docket No. 50-445
,O TABLE 3.3-5
( ENGINEERED SAFETY FEATURES RESPONSE TIMES 1 s DELETEb RESPONSE TIME IN SECONDS INITIATION SIGNAL AND FUNCTION 3,, ggg 3,g, g, j
- 1. Manual Initiation JUSTd:t CATib'd I Safety Injection (ECCS) ~IYem 5 N. A. . j
- b. Containment Spray N.A I
- c. Aase "A" Isolation N. A.
- d. Phe"8" Isolation N. A.
- a. Purge and Exhaust Isolation N. A.
- f. Steam L ne Isolation M. A.
- g. Feedwater Isolation N.A.
- h. Auxiliary F dwater N.A.
~
- i. N.A.
Essential Ser (ce Water ~ J. Containment Cool ng Fans N. A. l
- k. Control Room Isola ion N. A.
- 1. Reactor Trip -
N. A.
- s. Start Diesel Generator N.A.
O i
- 2. Containment Pressure .-High-1 -
l
- a. Safety Injection (ECCS) i [27]I13 /[12)(5)
- 1) Reactor Trip 1 [2] )
- 2) Feedwater Isolation k [7]II) l
- 3) Phase "A" Isolation [17)(2)fg77)(1)
- 4) Purge and Exhaust Isolation 1 [25]III /[10)(2) ,
- 5) Auxiliary Feechmter i [60) 1
- 6) Essential Service Water S [32]II)/[47)(2) ;
7). Containment cooling Fans [55]III /[40)(2)
- 8) Control Room Isolation N.
9)~' Start Diesel. Generator .4, i[ j
. I 1
l k , COMANCHE PEAK - UNIT 1 3/4 3-37 . l l
. j
Docket Ilo. 50-445 ( TABLE 3.3-5 (Continued) ENGINEERED SAFETY FEATURES RESPONSE TIMES DNITIATINGSIGNALANDFUNCTION ML6E D RESPONSE TIME IN SECONDS
- 3. Pressurizer Pressure--Low lp' g
. Safety Injection'(ECC5) -j g ag- i [27]I }/[12]
- 1) Reactor Trip i [2] !
I
- 2) Feedwater Isolation 1 [73 ) !
1 Phase "A" Isolation i [17](2)/[27]III
- 4) Purge and Exhaust Isolation. 1 [253 III /[10)(2)
- 5) xiliary Feeduster i [60]
- 6) Es ntial Service Water i [47]II)/[32)(2) j
- 7) Con nment Cooling Fans 1 [55](1)/[403(2)
- 8) Contro Room I' solation ,
M. A. . l
- 9) Start 01 el Generators ,
.$ [103
- 4. Differential Pressure etween Steam Lines-High'
- a. Safety Injection ( CS) i [22]I")/[123(5)
- 1) Reactor Trip < [2] I
- 2) Feedwater Isolatio [7]I3) l
- 3) Phase "A" Isolation i[17]I)/[27](1) '
- 4) Purge and Exhaust Isol ion i [25]II)/[10)(2)
- 5) Auxiliary Feedwater i [60]
- 6) Essential Service Water 1 [32)(2)fg47)(1)
- 7) Containment Cooling Fans 1 [55]II)/[403(2)
- 8) Control Room Isolation N.A.
J) Start Diesel Generators 1 [103 j
- 5. Steam Line Pressure--Low !
-a. Safety Injection (ECCS) i'[123(5)fgg)(4)
- 1) Ranctor Trip [2] !
- 2) : Feedwater Isolation ,i W I l 3) Phase "A" Isolation ~1 [1 (2)fgg7)(1) d
- 4) Pury and Enheest Ise'stlenI '
.- 1 (25] }/[10)(2) '
- 5) Auxiliary Feeester i [60]
- 6) Essential Service Water 1 [32)(2)f 7)(1)
- 7) Containment Cooling Fans 1 [55)(1)/[40 (2)
OMANCHE PEAK - UNIT 1 3/4 3-38
Docket No. 50-445 August 14, 1987 TABLE 3.3-5 (Continued)
.,O k
ENGINEERED SAFETY FEATURES RESPONSE TIMES 2NITIATING SIGNAL AND FUNCTION .[)h g g b RESPONSE TIME IN SECONDS
- 5. Steam Line Pressure--Low (Continued)SecLCb31 A
~
~
- 8) Control Room IsolationJOOTIPtCfrTttrJ N. A.
- 9) Start Diesel Generators Mem* I < [10]
- b. Steam Line Isolation IS3I3)
- 6. Contai'sqment Pressure--High-3 EI
- a. . Containment Spray 5 I45)(2)/[573 )
- b. Phasd "B" Isolation $ [55]III /[75](2)
- 7. Containment ssure--High-2 Isolation I3 Steam Li
\
= $ [93 )
E. Steam Flow in Tw'o Steam Lines--Migh s Coincident with T,\ Lowtow Steam Line Iso) tion 1,[930 )
- 9. Steam Line Pressure - gative Rate--High Steam Line Isolati i 19]I3) -
- 10. Steam Generator Water Level--High-High -
- a. Turbine Trip i [2.5] i
- t. Feedwater Isolatiott 1 [7]I3}
- 11. Stamm Generator Water Level-- J
- a. Mater-Driven Auxiliary ,
Faedwater Pumps $ I603
- b. Turbine-Driven Auxiliary -
Feedwater Pump i [603
- 12. Undervoltage RCP .,
Turbine-Driven Auxiliary Feechtster Pump i [50]
- 13. Loss-of-Dffsite Power Turbine-Driven Auxiliary Feedwater Pump 5,[60)
, it. Trip of All Main Feedwater Pumps All Auxiliary Feedwater Pumps N. COMANCHE FEAK - UNIT 1 3/4 3-39
Socket No. 50-445
% ust 14, 1987 TABLE 3.3-5 (Continued)
( ENGINEERED SAFETY FEATURES RESPONSE TIMES DWJTIATINGSIGNALANDFUNCTION E L ET e.b Response TIME IN sEcoNos N See LCo 3 2. 2
- 15. 5ktion Transfer on Low Pressur'OSTiFacsorJ iliary Feedwater (Suction Supply i I133 Au tic Realignment) Th AL 5
- 16. RWST Level--Logow
- a. Automatic Swi var to Containment Sump N.A.
- b. Coincident with Conta nt Sump
. Level--High and Safety ection
-(Automatic Switchover to Co inment .I# C1 Sump) -
' 1[25DJ }/I2ss3 )
- 17. Less of Power
- a. 4 kV Bus Undervoltage i 1103 (Loss of Voltage)
- t. 4 kV Emergency Bus i Undervoltage (Grid Degraded Voltage) .
,e " W e e 9 "
0MANCHE PEAK - UNIT 1 3/4 3-40
Socket No. 50-445
% ust 14, I W ,n TABLE 3.3-5 (Continued)
(\sj TABLE NOTATIONS 1 DELETED 3e e LCo 7. 2.a. JJST tFl CATtbV TA e m ** S D Diesel generator starting and sequence loading delays included. 4 (2) Diesel ne(tor starting and sequence loading delay $ included. j Offsite power aTa le. ; I
.(3) Air-operated valves. j 1
(4) Diesel generator starting a M sequence 1 delay included. RNR i l pumps not included. l (5) Diesel generator starting and sequenca leading delatys not i RHR pumps not included. 3 I
. f I
I l
~
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0MANCHE PEAK - UNIT 1 3/4 3-41
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Becket tio. 60-445
, INSTRUMENTATION N US$ E4e IIO7 .I b 3/4.3.3 MONITORING INSTRUMENTATION All m sTrurnenf func~ho* ns frorn RADIATION MONITORING FOR PLANT OPERATIONS fA ,3 L C o hwr 1 e eo mord,)or tetoeafed ape <- Ate 3 orNote q LIMITING CONDITION FOR OPERATION I
1 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alaru/ Trip Setpoints within the specified limits. APPLICABILITY: As shown in Table 3.3-5. ACTION: .
- a. With a radiation monitoring channel Alats/ Trip Satpoint for plant operations exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours or declare the channel inoperable. -
- d. With one or more radiation monitoring channels for plant operations J inoperable, take the ACTION shown in Table 3.3-6.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
( . SURVEILLANCE REQUIREMENTS 2
- J< e ' 7<*J/e Mark-ujo )
4.3.3.1 Each radiation monitoring instrumentation channel-for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL , CALIBRATION.and ANALOG CHANNEL OPERATIONAL TEST
- for the ICDES and at the frequencies shown in Table 4.3-3.
1 COMANCHE PE5K - UNIT 1 3/4 3-47
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COMANCHE PEAK - UNIT 1 3/4 3-49 l
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Decket No. 50-445 ) TABLE 3.3-6 (Continued) . August M, N TABLE NOTATIONS i Must satisfy Specification 3.11.2.1 requirements. ;
)
** With irradiated fuel in the fuel storage pool areas.
]
*** With fuel in the fuel storage pool areas. j lok!OITied ACTION STATEMENTS CodoWooN i ACTION 26 - With less than the Minimum Channels OPERABLE requirement, Leo 3,r.2. 8 opert. tion may continue provided the containment purge and Leo'2 0 + B exhaust valves are maintained closed. ,
CoWoopoN i , ACTION 27 - With the number of OPERABLE channels one less than the Minimum j tco 3.4.11 +dI Channels OPERABLE requirement, within 1 hour isolate the 1 g.c. 3, g, g. C. Control Room Emergency Ventilation System and initiate operation of the Contec1 Room Emergency Ventilation System in the ! recirculation mode. , i ACTION 28 - With less than the Minimum Channels OPERABLE requirement, opera-SEE mte M tion may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alam Setpoint is , provided in the fuel storage pool area. Restore the inoperable i monitors to OPERABLE status within 30 days or suspend all ! operations involving fuel movement in the fuel storage pool means. ' Cocoinav ACTION 29 - With less than the Minimum Channels OPERABLE requirement, J.co 3.344 f8 comply with the ACTION requirements af .5 specification 3.4.6.1. 1 ACTION 30 - With the number of OPERABLE channels less than required by the
$6s Note e 3 Minimum Channels OPERABLE requirements, initiate the preplanned !
alternate method of monitoring the appropriate parameter (s), within 3
~72 hours, and: - ;
- 1) either restore the inoperable Channel (s) to OPERABLE j status within 7 days of the event, er !
i
.2) . prepare and submit a Special Aapert to the Commission
. pursuant to Specification 5.9.2 within 14 days following i the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring y the system to OPERABLE status. !
1 a 1 e CDMANCHE PEAK - UNIT 1 . 3/4 3-50
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Socket No. 50-445 , August 14, 1987- j INSTRUMENTATION i The numben ' n the, @ feferf += i k ACCIDENT MONITORING INSTRUMENTATION L,co 321 W3TtFicATiorJ "I"+cmn LIMITING CONDITION FOR OPERATION
.2.3 3.a. 3 - 1 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3. .
~
ACTION: ]
- a. With the number of OPERABLE accident monitoring'lastrumentation J channels less than the Total Number of Channels shown in 3,s3 lTable 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least NOT STAND 8Y within the next 6 hours and in at least HDT SHUTDOW within the fa11 swing 6 hours.
No
- b. With the --M e' OPERABLE accident monitoring instrumentation channels except *'- "-it ::rt 'i@ er;: --Me ; ::-'*- , crf *le @
m et:- . elie'-hi;;5 : ;: redd eti- r:-i te , 'e:S t' - t'- "' '- - W Cte-n:1: OnE*AELE ---t:= -te e' Td'e 3. 3-10 restore the inoper-able channel (s) to OPERABLE status within 48 hours or be in at least ( HDT STANDBY within the next 6 hours and in at least NOT. SHUTDOWN within the following 6 hours.
- c. With the number of OPERABLE channels for the - 't _=t-? r;:@ j
.r Me ::: rr-4 te . e- t'e 5+ - --"e' '* ? : ; -"* -t *- = -i te-e- the containment atmosphere-high range radiation monitor, as-4Ae.
----ter ere! ant ediatie- 'e"e' ---4te- less than required by the Minimum Channels OPERABLE requirecants, initiate an alternate method of monitoring the appropriate parameter (s), within 72 hours, and. I c'th:- - : tere t' 4 :;:t'e ^ --- 5(e) *= 2 r ^*'_! ete+= "*t' 7 = - ; =; -- = - - it
; = m ; : , t- & t --i:-i , :=
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- d. The provisions of.5 specification 3.0.4 are not applicable. f SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation eennel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-7.54323.I J4 3.a,3,JL I
/COMANCHI PEAK - UNIT 1 3/4 3-63 )
1 _ _ - _ _ _ _ - - - _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ - l
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/ Sooket tio. 50-445 C INSTRUMENTATION , b b[h. A OM9USt I4, 1987 CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION I
3.3.3.7 Two independent Chlorine Detection Systems, with their Alarm / Trip ' Setpoints adjusted to actuate at a chlorine concentration of less than or - i equal to 5 ppe, shall be OPERABLE. APPLICABILITY: All MODES. ACTION: ,
- a. With one Chlorine Detection System inoperable, restore the inoperable system to OPERABLE status within 7 days or within the next 6 hours initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation. l
- b. With both Chlorine Detection Systmas inoperab'le, within I hour :
initiate and maintain operation of the Control Room Emergency ventilation System in the recirculation mode of operation. ,
- c. The provisions of Specification 3.0.4 are not applicable.
O - l SURVEILLANCE REQUIREMENTS 4.3.3.7 Each Chlorine Detection System shall be demonstrated OPERABLE by ; perfomance of a CHANNEL CHECK at laast once per 12 hours, an ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least 1 once per 18 months. i s O COMANCHE PEAK - UNIT ,1 3/4 3-68
R4bcw j Docket No. 50-445 L August 14, 1987 INSTRUMENTATION S6C DTb {.[ FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a min 5n, the fire detection instrumentation for each fire detection I zone shown in Table 3.3-11 shall be OPERABLE. APPLICABILITY: Whenever equipment protected by the fire detection instrument l 1s required to be OPERABLE. , i ACTION:
- a. With any, but mt non than one-half the total in any fire zone, <
Function A fire detection instruments shown in Table 3.3-11 inoperable. l restore the inoperable instrument (s) to OPERABLE status within ! 14 days or within the next I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once l per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours (or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.6). .
- b. With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any k Function B fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in l
Table 3.3-11 inoperable, within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least i ence per hour, unless the instrument (s) is located inside the contain-ment, then inspect that containment zone at least once per B hours 1 (or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.6).
- c. - The provisions of Specifications 3.0.3 and 3.0.4 an mt applicable. l I
SURVEILLANCE REQUIREMENTS i 4.3.3.8.1 Each of the above required fire detection instruments which are
' accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a 11tIP ACTUATING DEVICE OPERATIONAL TEST. Fire ,
detectors which are not accessible during plant operation shall be demonstrated ' OPERABLE by the performance of a TRIP ACTUATING DEYICE OPERATIONAL TEST during each COLD.SHLTTDOWN anceeding 24 hours unless performed in the previous 6 months. y 4.3.3.8.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alams of each of the above required fire detection instruments shall be demonstrated CPERABLE at least once per 6 months. 4.3.3.8.3 The nonsupervised circuits, associated with detector alarms, between the instrument and the control room shall be demonstrated OPERABLE at least once per 31 days. - COMANCHE PEAK - UNIT 1 3/4 3-69
Qa_\ccdd Booket No. 50-445 August 14, 1987 TABLE 3.3-11 f
A FIRE DETECTION INSTRUMENTS 1
TOTAL NUMBER INSTRUMENT LOCATION OF INSTRUMENTS * [ Illustrative) HEAT FLAME MSKE (x/y) (x/y) y.
- 1. Cor.tainment **
~
- a. Zone 1 Elevation
- b. Zone 2 Elevation
- 2. Control Room
- 3. Cable Spreading l
- a. Zone-1 Elevation
- b. Zone 2 Elevation
~
4 Computer Room
- 5. Switchgear Room ,
- 6. Remote Shutdown Panels
- 7. Station Battery Rooms
- 6. Turbine ,
- n. Zone 1 Elevation'
- b. Zone 2 Elevation . .
- 9. Diesel Generator
- a. Zorc 1 Elevation
- b. Zone 2 Elevation 1D. Safety-Belated Pumps l
- a. Zone 1 Elevation ~
- b. Zone 2 Elevation
- 11. Fuel. Storage
- a. Zone 1 Elevation -
~
- b. Zone 2 Elevation
[ List all detectors in areas required-to ensure the OPERABILITY of safety-
> related equipment.)
*(x/y): x is number of Function A (early warning fire detection and notification only) instruments.
y is number of Function 5 (actuation of Fire Suppression' l Systems and early warning and notification) instruments. s **The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A containment leakage rate tests. COMANCHE PEAK - UNIT 1 3/4 3-70 w
Ne{ Q Societ R. 50-445 1
. INSTRUMENTATION
[Q Gy{ ' O- LOOSE-PART DETECTION SYSTEM , LIMITING CONDITION FOR OPERATION , 3.3.3.9 The Loose-Part Detection System shall be OPERABLE. ; APPLICABILITY: MODES I and 2. ACTION:
- a. With one or more Loose-Part Detection System channels inoperable for more than 30 days, prepare and submit a Special Report to the i Commission pursuant to Specification 5.9.2 within the next 10 days !
outlining the cause of the malfunction and the plans for restoring the channel (s) ta OPERABLE status.
- b. The provisions of Specifications 3.D.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
~ .
4.3.3.9 Each channel of the Loose-Part Detection Systems shall be demonstrated OPERABLE by performance of:
- a. A CHANhEL CHECK at least once per 24 hours,
- b. An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, and
- c. A CHANNEL CALIBRATION st least once per.38 uneths. }
1 i l V l 1 d l COMAN'CHE PEAK - UNIT 1 3/4 3-71 l
Docket No. 50-445 3 UI b INSTRUMENTATION gg Q7g '
\ RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
! LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alars/ 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 (00CM). APPLICABILITY: At all times. ACTION:
- a. With a radioactive liquid effluent monitoring instvumuntation 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 ndicactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3. 3-12. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specifi-cation 6.9.1.4 why this inoperability was not corrected in a timely manner.
- c. The provisions of Specifications 3.0.3 and 3.0.4. are not applicable.
SURVEILLANCE REOUTREMENTS 4.3.3.10 Each radioactive liquid effluent senitoring instrumentation channel
'.shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the
' frequencies shown in Table 4.3-8. ,
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/ - SEE tha 1 m E 3.3. u cContinued3 August i , i m i
f ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the ' Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzad in accordance with Specif1 cation 4.11.1.1.1, and
- b. At least two technically qualified members of the facility staff independently verify the release rata calculations I and discharge line valving.
Otherwise,' suspend release of radioactive affluents via this pathway. j ACTION 36 - With the number of channels OPERABE 1ess than vequired try the Minimum Channels OPERABLE requirement, effluent releases via ; l this pathway may continue provided grab samples are analyzed for rac'ioactivity at a lower limit af sietection of no more than 10 7 microcurie /al: . ,
- a. At least once per 12 hours when the specific activity of 4 b.
the secondary coolant is greater than 0.01 aicroCu-ia/ gram DOSE EQUIVALENT I-131, or . At least once per 24 hours when the specific activity of ! the secondary coolant is .less than or equel to 0.01 microcurie / gram DOSE EQUIVALENT I-131. ACTIDN 37 - With the number of channels OPERAR E less than required by the Minimum Channels OPERABE requirement, effluent releases via
- this pathway may continue provided that, at least once per ,
12 hours, grab samples are es11ected and analyzed for radio- , activity at a lower limit of aletaction of no more then j 10 7 microcurie /m1. j
~ ACTIONt 38 - ' With the number of channels WERABE 1ess than required by the Minimum Channels OPEAABLE requirement, effluent releases via this pathway any continue provided the flew reta is estimated
- at least once per 4 hours during actualiveleases'. Pump perfor- i mance curves generated in place may be used to estimate flow. 3 i
With the number of channels OPERAS E less than required by the ACTION 39'- i Minimum Channels OPERABLE requirement, effluents releases via ! this pathway may continue provided the radioactivity level is j determined at least once per 4 hours during actual reler**5 )
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a h (o c. a k + cd Docket No. 60-445 ust H . M87 h Qg [ 8 3 _ TABLE 4.3-8 (Continued) TABLE NOTATIONS (1) The ANAL'0G CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any -l
' of the following conditions exists: I i
- a. Instrument indicates measured levels above the Alam/ Trip Setpoint, or ,
- b. Circuit failure, or
- c. Instrument indicates a downscale failure, or j
- d. Instrument controls act set in operata moda.
(2) TheANkt0G'CHANNELOPERATIONALTESTshalTalsodemonstratethatcontrol ; room alarm annunciation occurs if any of the fallowing conditions exists:
- a. Instrument indicates measured levels above the Alars Setpoint, or i
~
- b. Circuit failure, or ,
- c. Instrument indicates a downscale failure, or
- d. Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NES) or using standards that have been obtained from suppliers that parti:ipate in measurement assurance activities with N85. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related . to the initial calibration shall be used. j l (4) CHANNEL CHECK shall consist of verifying indication of flow during periods l of telease. CHANNEL CHECK shall be made at least c,nce per 24 hours on ; days on which continuous, periodic, or batch releases are made. 4 G* l COMANCHE FEAK - UNIT 1 3/4 3-78 ,
0" Godet No. 50-445 INSTRUMENTATION h6c (( f'J RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.11 The radioactive gaseous affluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alam/ Trip setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded. The Alam/ Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance witA the methodology and parameters in the ODCM. APPLICABILITY: As shown in Table 3.3-13 ACTION: ,
, a. With a radioactive gaseous effluent monitoring instrumentation channel Alam/ Trip Satpoint less conservative than required by the above specification, immediately ruspend the release of radioactive gaseous affluents monitored by the affected channel, or declare the channel inoperable.
- b. With less than the minimum number af radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE
/ status within 30 days and, if unsuccessful explain in the next Semi-g annual Radioactive Effluent Release Report pursuant to Specifica-tion 6.9.1.4 why this inoperability was not corrected in a timely manner. .
- c. The provisions of Specifications 3.D.3 and 3.D.4 mm not applicable.
i SURVEILLANCE REQUIREMENTS i 4.3.3.11 Each redisactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the. CHANNEL CHECK SOURCE i CHECK, CHANNEL CALIBRATION and ANMAG CH4pmEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.
. l CDMANCHE PEAK - UNIT 1 3/4 3-79
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l 2ebcAd jgg /Vpf g TABLE 3.3-13 (Continued) Socket tio. 50-445 August 14, 1987 w TABLE NOTATIONS
\
- At all times. ]
** During WASTE GAS HOLDUP SYSTEM operation.
ACTION STATEMENTS i ACTION 45.- With the number of channels SPERABLE less theo nquired by the Minimum Channels OPERABLE requirement, the conunts of. the tank (s) may be released to the environment provMad that prior-to initiating the release: )
- a. At least two fedapandant samples af the tarck's contants
.are analyzed, and
- b. At least two technically qualified members of the facility staff independently verify the release fata calculations and discharge valve lineup.
Otherwise, suspend release af radioactive effluents via this pathway. ACTION 45 - With the number of channels OPERABLE 1ess than required by the Minimum Channels OPERABLE requirement, effluent m1 eases via this pathway may continue provided the flow rata is estimated at least once per 4 hours. ACTION 47 - With the num$er of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at i least once per 12 hours and these samples are ane4yzed for 1 radioactivity within 24 hoves. j ACTION 48 - With the number of channels OPERABLE lees than required try the l Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive affluents via this pathway. : ACTION 49 - With the number of channels OPERABLE less than required by the i'
. Minimum Channels OPERABLE requirement, operation of this WASTE
- GAS HOLDUP SYSTEM may continue provided grab samples are !
coilected at least once per 4 tumrs and analyzed within the following 4 hours. l
" ACTION 50 - With the number of channnels OPERABLE ene less then required by the Minimum Channels OPERABLE requirement, operation.ef this
~
system may continue provided grab samples are takan and analyzed ; at least esca per 24 hours. Mth both channels inoperable, 1 operation may continue provided grab samples are taken and analyzed ; at least once per 4 hours during dogassing operations and at least once per 24 hours during other operations. 4 , COMANCHE PEAK - UNIT 1 3/4 3-85
de/oc b/ . r Docket No. 50-445 X( Ab7N ] TABLE 3.3-13(Continued) August 14, 1987 {( . TABLE NOTATIONS (Continued) i l ACTION 51 - With the number of channels OPERABLE less than required by the' ! Minimum Channels OPERABLE requirement, effluent releases via ;
' the affected pathway may continue provided samples are contin- !
vously collected with auxiliary sampling equipment as required ! in Table 4.n-2. i ACTION 52 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply ~ to the recombiner. 1 l 1 i
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- Socket No. 50 445 Jee Mg j [] TABLE 4.3-9 (Continued)
August .14,1987 ; TABLE NOTATIONS At all times.
** luring WASTE GAS HOLDUP SYSTEM operation.
(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic . isolation of this pathway and control room alars annsawiation occurs if j any of the following conditions exista: I
- a. Instrument indicates measured levels above the Alam/ Trip 5etpoint, or J
- b. Circuit' failure, or -
f
- c. Instrument indicates-a downscale failure, or )
i
- d. -Instrument controls not sat in aparate mode. ;
i (2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control ! room alarm annunciation occurs if any of the following conditions exists:
- a. Instrument indicates meas' u red levels above the Alars Setpoint, or
- b. Circuit failure, or Instrument indicates a downscale failure, or
( t.
- d. Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Sureau of Standards (NES) or using standards that have been obtained from suppliers that participate . in measurement assurance activities with NBS. These standards shall permit l calibrating the system over its intended range of energy and measurement j range. For subsequent CHANNEL CALIBRATION . sources that have been related 1 to the initial calibration shall be ased.
- l I
~{4) The CHANNEL CALIBRATION shall include the use of standard gas samples !
containing a nominal: ! 1a. Dne volume percent hydrogen, balance aftregon, and
- b. Four volume percent hydrogen, balance nitrogen. . !
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples { containing a nominal: , j l a. One volume percent anypen, balance nitrogen, and i
- b. Four volume percent oxygen, balance nitrogen.
COMANCHE FEAK - UNIT 1 3/4 3-92 i
w - , ~ . Re/swkd Docket 8to. 50-445 INSTRUMENTATION O [h
- 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.
i APPLICABILITY: MODES 1, 2, and 3. ,
]
ACTION:
- a. With one stop valve er one governor valve per high pressure turbine steam line inoperable and/or with one reheat stop valve or one
~
reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERA 8LE status within 72 hours, or close at least one valve in the affected ste,as line(s) or isolate the turbine from the steam supply within the next 5 hours. i
- t. With the above required Turbine Overspeed Protection System otherwise inoperable, within 5 hours isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS ( 4.3.4.1 The provisions of Specification 4.0.4 are not applicable, 4.3.4.2 The above required Turbine Dverspeed Protection System shall be j demonstrated OPERABLE. ; i
- a. At least once per 7 days by cycling each of the following valves <
through at least one complete cycle from the running position:
- 1) [Four] high pressure turbine stop valves.
s 2) [Four] high pressure turbine governer valves, j
- 3) [Four] low pressure turbine reheat stop valves, and j l
- 4) [Four] low pressure turtime rehmet fatarcept valves. j
- b. - At least once per 31 days by direct observation of the movement of
. each of the above valves through one comp 1*ete cycle from the running position, c.- At least once per"18 sonths by perfomance of a OlMSEL CALIBRATION l on the Turbine Overspeed' Protection Systems, and
- d. At least once per 40 months by disassembling at least one of eacn of the above valves and performing a visual and surface inspection of valve seats, disks, and stems and verifying no unacceptable flaws or excessive corrosion. If unacceptable flows or excessive corrosion are found, all other valves of that type shall be inspected.
k CDMANCHE PEAK - UNIT 1 3/4 3-93
I Socket No. 50-445
~
g3 August 14, 1967 1 3/4.4 REACTOR COOLANT SYSTEM (f . 1,3M 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION ! STARTUP AND POWER OPERATION 1 LIMITING CONDITION FOR OPERATION . j l 1 _LCO 3 3.9 .q (3.4.1.1 All reactor coolant loops shall be in operation. - l 1 APPLICABILITY: MODES I and 2.* l
- Ccod.iNvh k ACTION: )
With leis than the above required reactor coolant loops in w..i. ion, be in at least HDT STANDBY within 6 hours. . SURVEILLANCE REQUIREMENTS ~ s R 3 ,3 ,4,1
,4.4.1.1 The above required reactor coolant loops shall be wrified in operation and circulating reactor coolant at least once per 12 hours.
I I 1
. 1 I
I l
_ Cross RePmnw & 3,3 4 3.p,\q l
*SeeSpecialTestExceptionsSpecification3.10.k
~ ~ .
d COMANCHE PEAK - UNIT 1 3/4 4-1
Socket No. 50-445 g'g t 34, N i O {REACTORCOOLANTSYSTEM NDBY LIMITING CONDITION FOR OPERATION ] LC.O S,35At least two of the reactor coolant loops listed below shall be 3.4.1.2 l OPERABLE with at least two reactor coolant loops in operation when the Reactor Trip System breakers are closed and at least one reactor coolant loop in opera-tion when the Reactor Trip System breakers are open:" l
- a. Reactor Coolant Loop [A] and its associated steam generator.and reactor coolant pump, l I
- b. Reactor Coolant Loop [5] and its associated steam generator and' reactor coolant pump, j
- c. Reactor Coolant Loop [C] and its associated steam generator and l reactor coolant pump, and ]
f d. Reactor Coolant Loop [D] and its associated steam generator and y reactor coolant pump. APPLICABILITY: MDE 3. ACTION: 1-a. b0hunen With lessA than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours or be L, in yT S TDOWN,within the next 12 hours. G. 1 hinb one reactor coolant loop in operation and the Reactor Trip System breakers in the closed position, within 1 hour open the Reactor c. cM4't"r WlDi hoU rrector*"**"'- coolant loop in operation,1saspend all sperations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate correctiva action to return the ; required reactor coolant laap to operation.
.5 SURVEILLANCE REQUIREMENTS :
F4. . A least~the above required reacter coolant pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying i co et bre ker alignments ~and indicated power availability. ]
...' T required steam generators shall be determined UPERABLE by verifying secondary side water level to be greater the er equal;ts [175) at least once hou 1
- {S.S. 2.
required Teactor coolant loops shall be verified in operation
- 4. 1.2.3 '
'and cih:ulating reactor coolant at least once per 12 hours.
N & b Lco M 5 F*All (1) reactor no operationscoolant pumps are maythat permitted be would doenergized for up of cause dilution to the I hour provided: Reactor Coolant System boron concentration, and (2) core outlet temperature is ; l
. saintained at least 10*F below saturation temperature.
6
/ COMANCHE PEAK - UNIT 1 3/4 4-2 ,
I j i Socket No. 50-445 33 '
"* ' 0 c
'{REACTORCOOLANTSYSTEM s.s. b '
l
'_ HOT SHUTDOWN LIMITING CONDITION FOR OPERATION
~ LCO At13. b .
least two of the loops listed below shall be OPERABLE and at least 3.4.1.3 one of these loops shall be in operation:" -
- a. Reactor Coolant Loop [A] and its associated steam generator and !
reactor coolant pump,**
- b. Reactor Coolant Loop [B] and its associated steam generator and f reactor coolar.t pump,** j
- c. Reactor Coolant Loop [C] and its associatgd steen generator and i reactor coolant pump,** I
- d. Reactor Coolant Loop [D] and its associated steam generator and reactor coolant pump,**
- e. RHR Loop [A], and
- 1. RHR Loop [B].
APPLICABILITY: MODE 4. ' ACTION: . - t l a. (, Ofl lM 011 k (, h With less than the above required loops OPERABLE, immediately l l initiate corrective action to return the required loops to OPERABLE status as soon as possible; if the remaining DPERABLE loop is an RHR Icopg be in COLD SHUTDOWN within 24 hours. I C.<onbtfibn b ~ j b. With no loop in operation, suspend all aperations involving a reduc- ; tion in boron concentration of the Reactor Coolant System and i immediately initiate corrective action to return the required loop l
% to operation.
~ r0du h LC,0 334 I*All reactor coolant pumps and RHR pumps may be doenergized for up to I hour provided: (1) no operations are permitted that would cause dilution vY the Reactor Coolant Systaa boren concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.
**A reactor coolant pump shall not be started with one or more of the Reactor ,
Coolant System cold leg temperatures less than or equal to [275]*F unless the secondary water temperature of each steam ponerator is less than 'F above each of the Reactor Coolant System cold og temperatures. L 4 d CDMANCHE PEAK - UNIT 1 3/4 4-3
Docket No. 30-445 August 14, 1987 i REACTOR COOLANT SYSTEP e i HOT SHUTDOWN SURVEILLANCE REOUit.d.HENTS SR S 'hh,3 4
.4.1.3.1 The required reactor coolant pump (s), if not in operation, shall be i determined OPERABLE once per 7 days by verifying correct breaker alignments and ,
indicated l
'L4.SR s.9.
kI power availabi ity.
- 4. I'. 3. 2 The required steam generator (s) shall be determined OPERABl.E by l
t verifying secondary side water level to be greater than or equal to [17N at ;
- lea nce per 12 hours. i 4.4. . $,3,.3 At(p,least R one reactor coolent or RHR loop shall be verified in operation and circulating reactor coolant at least once per .22 hours.
l (
\ .
e e W ( d COMANCHE PEAK - UNIT 1 3/4 4-4
1 I l 3,3 Docket No. 50-445 August H , 1987 p REACTOR COOLANT SYSTEM l 0 U DOWN - LOOPS FILLQ i LIMITING CONDITION FOR OPERATION L.Co 3,t Aleast 3 ~7one residual heat removal (RHR) loop shall be OPERABLE and I 3.4.1.4.1 j in operation *, and either:
- a. One additional RHR loop shall be DPERABLE** or $
i
- b. The secondary side water level of at least two steam generators I shall be greater than [173%. l APPLICABILITY: MODE 5 with reactor coolant loops f511ad***.
ACTION: i CNE ?IOY b With one of the RHR loops inoperable or with less than the required I i
- a. j steam generator water level, immediately initiate corrective action .
to return the inoperable RHR loop to OPERABLE status or restore the required steam generator water level as soon as possible. n R oop in operation, suspend all operations involving a Eb. reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR { loop to operation. ; L . SURVEM. LANCE REQU,IREMENTS ! L M M "i'7 E I~4.4I1'.'4.1.'l 'TN ' secondary side water level of at least two steam generators I when required shall be determined to be within ilmits at least once per , 1[4.4. I'i . .I.,$,7, 2 At least S. one RHR loop shall be detetirined to be in operation and ;
, circulating reactor coolant at least once per 12 hours. .
No+es to LCD SSM J i
*The RHR pump may be deenergized for up to.1 hour provided: (1) no operations 1 are permitted that would cause dilution of the Reactor Coolant System boron 1 concentration, and (2) core outlet temperature is maintained at least 10*F I I
below saturation temperature.
**0ne RHR loop may be inoperable for up to 2 hours for surveillance testing !
provided the other RNR loop is OPERABLE and in operation. !
***A reactor coolant pump shall not be started with one or more of the Reactor
, Coolant System cold leg temperatures less than or equal to [275)*F unless I the secondary water temperature of each steam generator is less than *F above each of the Reactor Coolant System cold leg temperatures. .-~
L --. .
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COMANCHE PEAK - UNIT 1 3/44-5
3,3 Docket no. 50-445 ; REACTOR COOLANT SYSTEM August 14, 1987 l / - 3'g { OL ' SHUT 00WN - LOOPS NOT FILLED l LIMITINGCONDIT"]hNFOROPERATION ; 1
~ -LCO S3.S 3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE
- and at l gleast one RHR loop shall be in operation.** l APPLICABILITY: MODE 5 with reactor coolant loops not filled.
ACTION: iJ. p CONC ID0n Ti ! I
- a. With less than the above required RHR loops OPERA 8LE, immediately j initiate. corrective action to return the required RHR loops to .
OPERABLE status as soon as possible. )
- 3. Conlition B \
With no RHR Toop in operation, suspend all operations involving a i reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the requfred RHR l loop to operation. , n l SURVEILLANCE REQUIREMENTS SR 3.3.% l b.4.1.4.2 At least one RHR loop shall be detemined to be in operation and circulating rea9 tor coolant at least once per 12 hours. r --- Nk'68 0 EbO 3.6,3
$0ne RHR loop may be inoperable for up to 2 hours for surveillance testing ~
1 provided the other RHR loop is OPERABLE and in speration.
**The RHR pump may be deenergized for up to I tipur provided: (1) no opera-tions are pemitted that would cause dilution of the Reactor Coolant System I boren concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature. <
q .
] COMANCHE PEAK - UNIT 1 3/4 4-6
i 7 hi3 h t No. 50-445 August 14, 1987 - 10 LREACTORCOOLANTSYSTEM 1
- 3. s. n
- ISOLATED LOOP (OPTIONAL)
LIMITING CONDITION FOR OPERATION
- LCo 3 310 w -
3.4.1.5 .The baron concentration of an isolated loop shall be maintained greater than or equal to the boron concentration of the operating loops. ! APPLICABILITY: MODIS 1, 2, '3, 4, and 5. DD l ens A l B of W S S i4 Yb$kW With the requirements of tb above specification nok satisfied, do not open 3,3,/[ the isolated loop's stop valves; either increase the boron concentration of the isolated loop to within the limits within 4 hours or be in at least HOT STANDBY within the next 6. hours with the unisolated portion of the RCS borated to a SHUIDOWN MARGIN equivalent to at least 3% Ak/k at 20D*F.
~
.I cA b
SURVEILLANCE REQUIREMENTS J bf $* brko T 4.4.1.5 The boron concentration of an isolated loop shall be detenrined to be l greater than or agual to the boron concentration of the operating loops at i least once per 24 hours and within 30 minutes prior to apening either the hot 1eg or cold leg stop valves of an isolated loop. . 1
- i, 1
-S*
/COMANCHEPEAK-UNIT 1 3/4 4-7
. 1 Docket ti6. 50-445 >
13 REACTOR COOLANT SYSTEM August 14, 1987 , e u k 50 LATED LOOP STARTUP 10PTIONAL) i
~
LIMITING CONDITION FOR OPERATION
- LCo ,S S,lO i 3.4.1.6 A reactor coolant loop shall remain isolated until: )
- I
- a. The isolated loop has been operating on a recirculation flow of greater than or equal to gpa for at least 90 minutes and the -
l temperature at the cold leg of the isolated loop is within 20*F of the highest cold leg temperature of the operating loops, and , i
- b. The reactor is suberitical by at least IX Ak/k. i
" J APPLICABILITY: All MODES. .
ACTION: - . rWith theCrequirements Ontd[l0t1 of the above specification not satisfied, suspend startup of the isolated loop. SURVEILLANCE REQUIREMENTS _ SR 3,3, ID, / 4.4.1.6.1 The isolated loop cold leg temperature shall be detemined to be within 20*F of the highest cold leg temperature of the aparating loops within 0 a n te p to to pening the cold leg stop valve. I 4.4.1.6.2 The reactor shall be determined to be saberitical by at least i 1% Ak/k within 30 minutes prior to apening the cold leg stop valve.
,
- I
. i s .
d COMANCHE PEAK - UNIT 1 3/4 4-8
(f. (illif bC, 90cket No. 50 445
~
fbl~ NOf"& l August 14, 1987 p REACTOR CDOLANT SYSTEM 3/4.A.2 SAFETY VALVES i SHUTDOWN LIMITING CONDITION FOR OPERATIDH 3.4.2.1 A minimum of one pressurizer Code safety valve shall be OPERABLE with a lift setting of 2485 psig t 1%.* , APPLICABILITY: #CDES 4 and 5. ACTION: With no pressurizer Code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an DPERABLE RHR loop into operation in the shutdown cooling mode. SURVEILLANCE REQUIREMENTS 4.4.2.1 No additional requirements other than those required by Specification 4.D.5. I 1 1
\
i I
"Ti.. 'ift setting pressure shall correspond to ambient condit hns of the valve t nominal operating temperature and pressure.
d COMANCHE PEAK - UNIT 1 3/4 4-9
3,3 e.aketso.s0445 Aangust 14, 1987 REACTOR COOLANT SYSTEM 1,Oi 3.3.)R 9Q - OPERATING LIMITING CONDITION FOR OPERATION
$li b*E, l2
- b. 4. 2. 2 All pressurizer Code safety valves shall be DPERABLE with a lift setting of 2485 psig 2 1%.*
- 1 APPLICABILITY: MODES l' 2, and 3.
ACTION: l With8 Nuriz r safety valve faoperable, either restore the j inoperable valve to OPERABLE status within 15 minutes or be in at least HOT i STANDBY within 6 hours and in at least HOT SHLTTDOWN within the following .
;6 hours. !
SURVEILLANCE REQUIREMENTS Q' SR 3.3.12,1 Specification 4.0.5. 4.4.2.2 No additional requirements other than those required by i A0% to LCo 3.3,1l2. p*The lift setting pressure shall correspond to ambient conditions of the valv at nominal operating temperature and pressure. l O
' / COMANCHE PEAK - UNIT 1 3/4 4-10 O
_ _ _ _ . - _____m______ ._
Soaket Ilo. 50-445 33 REACTOR COOLANT SYSTEM b /2'4h3 PRESSURIZER LIMITING CONDITION FOR OPERATION l L C O 3 3 .Il 3.4.3 The pressurizer shall be OPERABLE with a water volume of less than or l equal to [1656) cubic feet, and at least two groups of pressurizer heaters l each having a capacity of at least [150] kW. . APPL]CABILITY: MODES 1, 2, and 3. ACTION: a. Conk
- ho.ne BID With only one grolrp of pressurizer hesters OPERABLE, vestore at least i
two groups to DPERABLE status within 72 hours or be in at least NOT ' i STANDBY within the next 6 hours and in HDT .56tJTDOWN within the fo119 wing'6 hours. ' L , 9 i
- b. L'00DiflorlS $ C,/r'ot Withthepressufiz rwise inoperable, beln at least HOT STANDBY' !
with the Reactor Trip System breakers open within 6 hours and in HDT SHUTDOWN within the following 6 hours. , O . i SURVEILLANCE REQUIREMENTS SR S.S.H. I 4.4.3.1 The pressurizer water wohne shall be determined to be within its per 12 hours. ' limitkttaastoeS.3. S 1, I4.4.3.2 The capac ty of each of the above required grings af pressurizer heaters shall be verified by energizing the heaters and measuring circuit curren at least once per 92 days. .- c S 3 3 D,3 4.4.3. The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 28 aanths by manually transferring power from the normal to the amargency power supply and energizing the heaters. e CDMANCHE PEAK - UNIT 1 3/4 4-11
14-b. I , $,3 Socket No. 50-445 REACTOR COOLANT SYSTEM A"9"50 I4' 1987 I i *
/ . 4."a RELIEF VALVES
- j
. I LIMITING CONDITION FOR OPERATI s
' l
~ Lc4 3,1G .
3.4.4 All power-operated relle Ivalves (PORVs) and their associated block valves shall be OPERABLE. ;* ' 4 APPLICABILITY: MODES 1, 2, ACTION: ' 00n6iklDI,s A D >
- a. With one or more 7bRV(s) inoperable, because af excessive seat leak-age, within I hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s); otherwise, be in at least HOT STANDSY within the next 6 hours and in COLD SHUTD0lel within the fol-L n1 0 hour . 1
- b. win ne rable due to causes other than excessive seat leakage, within 1 hour either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following ,
72 hours or be in HOT STANDBY within the next 6 hours and in COLD j ( SHUTD , ,w ith the following 30 hours. LOR 1 Oh - l
- c. With both POR (s) inoperable due to causes other than sixcessive seat leakage, within I hour either restore each of the PORV(s) to OPERABLE status or close their associated block valve (s) and remove ,
power from the block valve (s) and be in HOT STA28Y within the next l
" ~ '
l l n d. QYeo D hon Y With[oneormoreblock alve(s) inoperab'e, within I hour (1) restors the 61o u va ve s PERABLE status or close the block valve (s) and i remove power from the block valve (s); or close the PORY and remove j power from its associated solenoid valve; and (2) apply ACTION b j above, as appro a for the isolated PORV(s). j e. tJove f A Theprovisfonsof rgry Apfeation3.0.4arenotapplicable. i
]
" 1 SURVEILLANCE REQUIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be st a QPERABLE at least once per 18 months by:
- a. Operatin )
g.b. SR 3,3,gl32. the valve through one complete cycle of full travel, and Perfoming a CHANNEL CALIBRATION of the actuation instrumentation. COMANCHE PEAK - UNIT 1 3/4 4-12
D I Docket Wo. 50-445 REACTOR COOLANT SYSTEM k 3/4.4.4 RELIEF VALVES l SURVEILLANCE REQUIREMENTS s SR S.S. lS l i 4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per j 92 days by operating the valve through one complete cycle of full travel .I unless the block valve is closed in order to aset the requirements of ACTION a I dndb edification 3.4.4. ) m o 3, l3, Y i 4.4.$4. e emergency power supply for tte PORVs and block valves shall be j demonstrated DPERABLE at least once per 18 months by: . j
- a. Manually transferring motive and control power from the norma; to !
the emergency power supply, and -
- b. Operating the valves through a complete cycle of full travel.
l 1 (* . I
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1 1 e COMANCHE PEAK - (JNIT 1 3/4 4-13
1 l DOoktt el0 50*445 Se /~ a hc! d dl' ' da- [S frlNe I 4 REACTOR COOLANT SYSTEM bM
- i 3/4.4.5 STEAM GENERATORS LIMITING CONDITION FOR OPERATION' 3.4.5 Each steam generator shall be OPERABl.E. l
. i APPLICABILITY: ElDES 1, 2, 3, and 4. .,
j ACTION:
~ With one or more steam generatorsinoperablerTes'.1pm the inoperable generator (s) ]
.ta OPERABLE status. prior to increasing T above 200*F.
SURVEILLANCE ret)UIREMENTS i 4.4.5.0 Each steam generator shall be deecnstrated DPERABEE by performance of the following augmented inservice inspection program and the requirements of j Specification 4.0.5. . 1 [ 4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator j
- g. shall be determined OPERABLE during shutdown by selecting and inspecting at i least the minimum number of steam generators specified in Table 4~ 4-1..
4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample site, inspection result classUication, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be performed at the fre-quencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. The 1 tubes selected for each inservice inspection shalllaclude at least 35 of the ,(
. total number of tubes in all steam generators, the tubes selected for these i
- inspections shall be selected on a random basis except: 1
- a. ~ Where experience in similar plants with sis 11er water chemistry 4 indicates critical areas to be inspected, then at least 50K of the d tubes inspected shall be from these critical areas; ]
- b. The first sample of tubes selected for each inservin inspection (subsequent to the preservice inspecties) of each uteam generator l shall include:
COMANCHE PEAK - UNIT 1 3/4 4-14 -
l r 6 DM D , O6 ' y3f 5 f i REACTOR COOLANT SYSTEM ' - i l STEAM GENERATORS (see Me IL) I 1 l SURVEILLANCE REQUIREMENTS (Continued) j [ h J l ! 1) All nonplugged tubes that previously had detectable wall I penetrations (greater than 205), -
)
- 2) Tubes in those areas whom experience has indicated potential f problems, and
- 3) A tube inspection (pursuant to Specification 4.4.5.4a.9) shall ,
be performed on each selected tube. If any selected tube does not permit the passage of the oddy current probe for a tube inspection, this shall be recorded and an adjacent tee shall be selected and subjected to a tube inspection. 1 1 I
- c. The tubes selected as the second and third samples (W Tequired by l Table 4.4-2) during each inservice inspection any be . subjected to a l partial tube inspection provided: l
- 2) The tubes selected for these samples include the tubes from l those areas of the tube sheet array where tubes with !
imperfections were previously found, and l r
\ 2) The inspections include those portions of the tens where l imperfections were previously found.
The results of each sample inspection shall be' classified into ane of the following three categorias: Catecery Inspection Results 1 C-1 ~ Less then 35 sf the total tubes inspected am j degraded tubes and none of the inspected tubes 1 are defective. C-2 One or1mem tees,$st art nGre than 1% of the 1 total t ees inspected are defective, or between 1 55 and 10E of the total tees inspected are j degraded tubes. q C-3 More than 10E of the total tubes inspected are degraded tubes or more than 2% of the inspected tubes are defective. Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentsge calculations. ( n COMANCHE PEAK - UNIT 1 3/4 4-15
W Q ()(, REACTOR COOLANT SYSTEM til 30V ' 99Cktt'9fo. 50-445 Ampust 14, 1987 , k , STEAM GENERATORS 0*eNdle-lbb SURVEILLANCE REQUIREMENTS (continued) 4.4.5.3 Inspection Frequencies - The above required inservice inspections of ! steam generator tubes shall be performed at the following frequencies: I
- a. The first inservice inspection shall be perfomed after 6 Effective Full Power Months but within 24 calendar months of initial criticality.
Subsequent inservice inspections shall be partomed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive-inspections, not including the preser- ! vice inspection, result in all inspection results falling into the C ' category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additianal degradation i f has occurred, the inspection interval my be extended to a maximum af j once per 40 months; ;
- b. If the results of the inservice inspection of a steam generator !
conducted in accordance with Table 4.4-2 at 40-month intervals fa"11 1 in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The inemase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3a.; the interval any then be extended to a ! aaximum of once per 40 months; and j (
- c. Additional, unscheduled inservice inspections shall be perfomed on I each steam generator in accordance with the first sample inspection ;
specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions: l
- 1) Primary-ta secondary tubes leak (not including leaks originating I from tube-to-tube sheet walds) in excess of the limits of i j
l :Specificatfoe 14.5.2, or
- 2) A seismic occurrence greater than the Operating Basis Earthquake, -
o 3) A loss-of-coolant accident requirin0 actuation of the Engineered 1 Safety Features, er !
- 4) A main steam line or faceseter line reak. l
( ( . ICOMANCHEPEAK-UNIT 1 3/4 4-16
- - - - - - - - - - - --__-____--_m__ . _ _ - . _ __ ._
l l y Q/gg p g Sooket Glo. 50-445 N "8l I4' I REACTOR COOLANT SYST M gj g)
, STEAM GENERATOR l SURVEILLANCE REQUIREMENTS (Continued)
I- J Acceptance criteria
^
4.4.5.4 -
- a. As used in this specification:
I 1) Imperfection means an exception to the dimensionr, finish, or ! I contour of a tube from that required by fabrication drawings or I specifications. Eddy-current testing indications below 20E mf .
^ "the nominal tube wall thickness, if detectable, ety be- 1 considered as imperfections; l ,
- 2) Degradation means 'a service-induced cracking..asasta0s, waar, er general corrosion accurring on either inside er autside of'a i tube;
- 3) Decraded Tube imeans a tube containing iv. d.iens ymater than or equal to 20E of the nominal wal) thickness caused by degradation; ,
- 4) E Decradatioj amans the percentage of the tuba wall thickness affectec or remove % by degradation; k Defect means an imperfection of such severity that'it exceeds 5) the plugging limit. A tube containing a defect is defective; l
- 5) Pluccino Limit means the imperfection depth at er beyond which '
the tube shall be removed from service and is equal to [403%* of the nominal tube wall thickness;
- 7) Unserviceable describes the condition of a tube if it leaks or -
'/ -
contains a aefect large enough to affect its structural integ- : rity in the event of.an Operating Basis Earthquake, a loss-of- l
. _ coolant accident, or a steam line or feedwater line break as j
.specified in specification 4.4.5.3c., above;
- 8) Tube inspection means an inspection of the stame generster tube i from the point of entry (hot leg side) coupletely around the i U-bend to the tap support of the sold leg; and I
~
*Value to be determined in accordance with the recommendations of Regulatory Guide 1.121, August 1976.
J l
-l
] CDMANCHE PEAK - UNIT 1 3/4 4-17
~
C (f, Docket No. 50-445 P L< (41 (4 36r A"9"'t 34' 1987 i REACTOR COOLANT SYSTEM ( e STEAM GENERATOR (Jee NS 16 I : SURVEILLANCE REQUIREMENTS (Continued) I
- 9) Preservice Inspection means an inspection of the full length of ,
eacn tube in each steam generator performed by eddy current i techniques prior to service to establish a baseline condition l' of the tubing. This inspection shall be perforseed prior to l initial POWER DPERATION using the equipment and techniques expected to be used during subsequent inservice Inspections.
- b. 7he steam generator shall be determined VPCRABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by 1 I
Table 4.4-2. i I 4.4.5.5 Reports !
; a. Within 15 days following the completion of each inservice inspection i
> of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a Special Report !
pursuant to Specification E.9.2; j
- b. The complete results of the steam generator tube inservice inspection ;
shall be submitted to the Commission in a Special Report pursuant to l Specification 6.9.2 within 12 months following the completion of the i inspection. This Special Report shall include: i
.1) Number and artent of tubes inspected, i
- 2) Location and percent of wall-thickness penetration for each ,
indication of an imperfection, and {
""3) ' Identification af tubes plagged.
- c. Results of. steam generator tube inspections which fall into Category ,
-C-3 shall be reported to the Commission persment to 10 CFR Part 50.72 1 and prior to resumption of plant operation. This report shall provide 1 a description of investigations co.1 ducted to determine cause of the 1 tube degradation and corrective asasures taken ta prevent recurrence. I i
d COMANCHE PEAK - UNIT 1 3/4 4-18
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~ 3,3 Docket.Wo. 50-445 August 14, 1987 REACTOR COOLANT SYSTEM g
A ::. 3.S. )it 4 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAK g DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION LLO 3.3. Ils 3.4.6.1 The following Reactor Coolant System Lankage Detection Systems shall be OPERABLE:
- a. The Containment Atmosphere [ Gaseous 1sr Particulate) Radioactivity
- Monitoring System,
- b. The Containment Pocket susp Level and Flow Monitoring System, and
- c. Eitner the [conta'inment air cooler condensate flow rate] or a Containment Atmosphere [ Gaseous er Particulate] Radioactivity Monitoring System.
APPLICABILITY: MDDES 1, 2, 3, and 4. - ACTION: ;. 1
- DOMETophb bj.b N 0 With only two of the abo 9e rdqu' ired Leakage lhttaction Systems DPERABLE, g operation may continue for up to 30 days provided grab samples of the contain-ment atmosphere are obtained and analyzed at least once per 24 hours when the t required Gaseous or Particulate Radioactive Monitoring System is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours.and in COLD i SHUTDOWN within the following 30 hours.
a _ SURVEILLANCE REQUIREMENTS 4.4.6.1 The Les e Detaction Systans shall be demonst d OPERABLE by: i a. S - 3. . b C tainmentAtmels reTee R3. 2-and 5,1 < uhrte Monitoring Systems-performance of CHANNEL CNECK, CHMSEL CALIBRATION,- and ANALOG CHANNEL .; OPERATIONAL TEST at the frequencies specif.ied in Table 4.3-3, 1 SR ES,IL,S , B. Containment Pocket Sung Level and Flow Monitoring System perf$rmance l y of CHANNEL CALIBRATION at least once per 18 saonths, and 1 1 ,
- c. [5pecify appropriate surveillance tests depending won the type of -
Leakage Detection System selected.) 6
~
COMANCHE PEAK.- UNIT 1 3/4 4-21
3Q Socket No. 50-445 REACTOR COOLANT SYSTEM L 3,s.14
'" OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION
- tco.3,3.H 3.4.6.2 Reactor Coolant System leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE. 4
- b. 2 GPM UNIDENTIFIED LEAKAGE. ,
I
- c. 1 GPM total reactor-to-secondary leakage L.Q. all stans generators not isolated from the Reactor Coolant System and
[500] gallons per day through any one steam generator not isolated from the Reactor. Coolant Systas,
- d. 10 GPM IpE#TIFIED 1.EAKAGE from the ammetar Coolant Systan, 8
e. L C.DGPM3. 44 - CONTROLLED LEAKAGE at a Anactor Coolant System pressure of
\
i Tfl5 1 20 psic, and 1 If. L CD 0.5 GPMS.3. l[ per nominal inch of valve size up to a anximum of leakage { 5 GPM at a Reactor Coolant System pressure of 2235 t 20 psig from any i Reactor Coolant System Pressure Isolation Valve specified in %. --- Table 3.4-1. , APPLICABILITY: tODES 1, 2, 3, and 4. ACTION: i.
,_ bon bI'lrfl k With any PRESSURE BOUNDARY LEAKAGE, be in at least HDT STANDBY ,
n.
, withir 6 ho s and in COLD SIRITDOWN within the followi $ lC hours. I 4
.. $.b..Lcwki?wns C 0 LE - . . .EamAus AEB E
,trith any Re e/ cdtflant System leakage greater tha
'above limits, excluding PRESSURE SOUNDARY LEAKAEE a
~
1 Reactor coolant 5ystem Pressure Isolation Valve , reduce the leakagf [f ]<
' rate to within limits within 4 nours or se in at least HDT STANDBY within the next 6 hours and ta' COLD SIRmMR$1 within.the following ec-- iWfth n"0I' ins k l 6 # Lco 3 3.15~
any Reactor.! Coolant System Pressure Isolation Valve leakage
~ .c.
greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least two closed manus.1 or deactivated automatic valves, 4 { or be in at least NOT STANDBY within the ner.t 6 hours and in COLD SHUTDOV4 within the following 30 hours. ; ( . COMANCHE PEAK - UNIT 1 3/4 4-22 -
Socket No. 50-445 4 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant Systes leakages shall be demonstrated to be within each of the abo e limits by: .
- Q,)E. Ptr LLO 3,3,14 J 0 dsfi dort . M Y.
- z. Monitoring the containment atmosphere [ gaseous or particulate) radioactivity monitor at laast ance per 12 hours;
- b. . Monitoring the containment pockat. sump inventory and discharge at L._ least on:e per 12 hours; c.
SR SA.41of the CONTROL!.ED LEAKAGE to the reactor coolant pump Measurement seals when the Reactor Coolant System pressure is .2235120 psig at least once per 31 days with the modulating valve fully open. The provisions of Specification 4.0.4 are act applicable far entry into L MODE 3 or 4; ' 1 r- d. SR 3.3, H.f oa Reactor Coolant System water inventory balance at Performance least once per 72 hours; and De,)C.tE,b 06r LLD 3,9,14 Jod8ica, tion 8 k, [ e. MonitoringIthe Reactor Head Flange Leakoff System at least once per 2 24 hours.
- 3 3, 15,1 4.4. 2.2 'Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated DPERABLE by verifying leakage to be with.n its limit: .
- a. At least once per 18 months,
- b. Prior to entering MDDE 2 whenever the plant has been in COLD
. - - SHUTDOWN .far .72 hours or_ more and if laakage testingshas not..been
. performed in the previons 9 months,
- r. ' Prior to returning the valve to service following maintenance, repair,or replacement work on the valve, and
' d. Within 24 hours following valve actuation due te.autamatic or manual action or flow through the valva.
- a. As outlined in the ASME Code, Section II, paragraph IW-3427(b). 1 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 er 4.
\
CDMANCHE PEAK - UNIT 1 3/4 4 _ - _ _ - .
h(-[M[ ?B.r b(D 13,lf )nb M Ilo 5 445 August 14, 1987 TABLE 3.4-1 i REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES
~
' VALVE NUMBER - FUNCTION l
e a \ l' e i
!l i
s COMANCHE PEAK - UNIT 1 3/4 4-24
i tw U REACTOR COOLANT SYSTEM i 3/4.4.7 CHEMISTRY LfMITING CONDITION FOR OPERATION 3.4.7 The Reactor Coolant System chemistry shall be maintained within the limits specified in Table 3.4-2. APPLICABILITY: At all times. . - ACTION: . MODES 1, 2, 3, and 4: I a. With any one er more thesistry parameter in excess of its 31, &- State Limit but within its Transient Limit, restore the parameter to
; within its Steady-State Limit within 24 hours or be in at least :NDT l STANDBY within the next 5 hours and in CDLD SHU1DOWN within the j following 30 hours; and .
- b. With any one er more chemist 1y parameter in excess of its Transient Limit, be in at leas't HOT STANDBY within 5 hours and in COLD SHUTDOWN !
within the following 30 hours. kO At All Other Times: . . J 1 l With the concentration of either chloride or fluoride in the Reactor coolant System in excess of its Steady-State Limit for more than 24 hours l or in excess of its Transient Limit, reduce the pressurizer pressure to ! less than or equal to 500 psig, if applicable, and perform an engineering ; evaluation to detemine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; detemine that the i Aeactor Coolant System remains acceptable for continued operation prior l to inemasing the pmssurizer pmasure above 500 psig or prior to i' proceeding to MODE 4. l
'5 SURVEILLANCE REQUIREMENTS .;
4.4.7 The Reactor Coolant System chemistry shall be determined:to be within t the limits by analysis of those parameters at the frequencies specified in Table 4.4-3. L --
. 1 COMANCHE PEAK - UNIT 1 3/4 4-25
r- - I L [k U6 7E l/ b I f g
> TABLE 3.4-2 e i REACTOR COOLANT SYSTEM CHEMISTRY LIMITS
- 5TEADY-STATE TRANSIENT l PARAMETER LIMIT LIMIT
)
Dissolved Oxygen * < 0.10 ppe 5 1.00 ppe Chloride < D.15 ppa 1 1.50 ppm Fluoride ;S 4.15 ppe .- 5 1.50 ppe , i
\
l i L .
" Limit not applicable with T,,, less than wr aqual to 25D*F.
e
]
4 1 COMANCHE PEAK - UNIT 1 3/4 4 __-
- , - ' g;C cg ON ' Ol~b i Socket No. 50-445 us .14, 1987 TABLE 4.4-3 I REACTOR COOLANT SYSTEM ~
CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS I SAMPLE AND ! PARAMETER ANALYSIS FREQUENCY t i k Dissolved Oxygen
- At least once per 72 hours I
j Chloride At least once per 72 hours ;
' Fluoride- At least once per 22 hours j I i i
)
l ( t
*Not required with T,yg less than or equal to 250*F 1
. 1 l
a t t COMANCHE PEAK - UNIT 1 3/4 4-27
Sedet No. 50-445 32 . August 14, 1987 O REACTOR COOLANT SYSTEM
= 3.s. n 3/4.A.8 SPECIFIC ACTIVITY l LIMITING CONDITION FOR OPERATION ;
- LCC 3,3,M i I
3.4.8 The specific activity of the reactor coolant shall be limited to:
- a. Less than er equal to 1 microcurie per gram DOSE EQUIVALENT I-131, and
- b. Less than or equal to 1004 alcroturies per gram of gross radioactivity.
APPLICABILITY: K) DES 1, 2, .3, 4, and 5. ]
)
ACTION: j Lonsdcns MODE 5 1, 2 and 3*: A) B J [& j
- a. With the specific activity of t.he Teactor coolant v.4w than l
'\ 1 sierocurie per gram DOSE EQUIVALENT I-131 for more than 48 hours !
during one continuous time interval or axceeding the limit line shown i on Figure 3.4-1, be in at least HOT STANDBY with Tavg 1ess than SDD'F within 6 hours; and (G b. With the specific activity of the reactor coolant greater than 1004 microcuries per gram, be in at least NOT STANDBY with T avs less than 500*F within 6 hours. MODES 1, 2, 3, 4, and 5: With the specific activity of the reactor coolant greater than 1 microcuris per gram DOSE EQUIVALENT I-131 or greater than 1004 micro- 3 Curies per gram, perfom the sampling and analysis requirements of Itan 4.a) '
.of Table 4.4-4 until the specific activity of the reactor coolant is i restored to within its limits. !
l SURVEILLANCE REQUIREMENTS j
.5R 3,3, n,) # r,qp SR 3,5,0, t-4.4.8 The specific activ' ty dT the reactor coolant shall be determined to be l within the limits by performance of the sampling and analysis prograa of i
{able4.4-4. .
.6 g
g y- To AffLICASErry, "With T,yg greater thar, or equct to 500'F. COMANCHE PEAK - UNIT 1 3/4 4-28
' Socket No.- 50-445
. ~ August 14, IM7
.\
l i
) \ ,
I
~
1 ti 1 i I igore 3,3, rz-l ; FIGURE 3.4-1. ; ! <. DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC
" ACTIVITY >1 pCi/ gram DOSE EQUIVALENT I-131 ,
O t s dCOMANCHE PEAK - UNIT 1 3/4 4-29
Ml #
' Au Sq 5
E HR f C 4 I S , I WSY 4 f 3 NL , I A 3 , 3 N # , SA , 2 E 2 2 ~ DD , ON , # MA 1 1 1 1 1 d
. n a e E s gg a L r e ,
f ,2nn .tu P u l oy ia l Ao M o f i1 t nwh Hh A h ,c R - S mi eot 2 ses 1av el E1 Y S 7 r pd 3 ri wlR H T I use 1 gt t oE Ta I S r
- o eE - / c efW%
VM Y e
- hecSIl a b O5Dn I A LY p
- hxO Co tP1Ei TR AC . s 4t eDTpi er Th CG NN e s h N d l u L gA t 4 AO AE c y t rrymEEa poA nRi
- R U n a n eet aL/r shMi e o pvirA0 Rde w.d 4 CP DQ o d evgv0s s6EehRo I NE m s eni/i1 HetEl 4 FS II AR t E
F s a 4 1 6 cetl u nhcCqrr nn o 'e d T c xfOe Wr - f E CS e r Ot a pE o g OaaeoPp L EY L e r B PL P l e e . A SA M p p T N A t ) ) TA S A 1 1 a b N
- AD LN -
OA O gA-R C l ,V ).*o 5 3 T C O
}
7u nt lq l
, 1 1
A E l gE k 3. igend k
- 3 .gSOn s gldaon Do3 3 grtis l 3
3 e1 oa+E Qt i y v sn i e t r r oi, s f - 1 T _i sc f s1 y3 N t n yn E co s o l l1 M a aC a a-E RS ia od na1 c nI i A UI dn 3 m g _ SS ai c1 e cn h AY EL MA se o Rmi- pI c pd o ou fi N st tT l tl _ FA oe oN d oc _ O rD sE e sn _ D G I L R II EN PA Y . . . . - T _1 2 3 4 - f J l i I - (" n%,{,EZ . ': 1* i5
Dooket Ilo. 50-445 [' TABLE 4.4-4 (Continued) TABLE NOTATIONS ] i
'*Foo note,de eted - .
gg F,**Arabo of the specificemkca activityanalysis for I shall except for each radionuclides, consist of the quantitative for radionuclides with half-lives less than 10 minutes and all radiciodines, which is identified in the reactor coolant. The specific activities f r these individual radio-nuclides shall be used in the determination of for the reactor coolant sample. Determination of the contributors to i shall be based upon those peaks identifiable with a 95% confidence level. ener f***sampIJtot 3.3, n,3 1 ta en after a minimum of 2 EFPD and 20 days of POWER OPERATION j sed si e reactor was last subcritical for 48 hours or longer. _ havern el p$tb n W Ie speci ic activity of the Reactor Eoclant System is restored T#U L within its limits. s k - . I I
.i l
I 4 1
. k
~
O COMANCHE PEAK - UNIT 1 3/4 4-31
I n n Docket No. 50-445
.- ), O August 14, 1987
.( {REACTORCOOLANTSYSTEM i
3 /t. d . 9' PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM i LIMITING CONDITION FOR OPERATION L CO 3,3,3 .
}
3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and insarvice leak and hydrost.atic testing with: 3
- a. A maximum heatap of IIO07F in any 1-hour period,
{ l b. A maximum cooldown of [1007F in ary 1-hour #od, and ^
- c. A maximum temperature change of less than or equal to IID7F in any )
i 1-hour period during inservice hydrostatic and laak tasting aparations above the heatup and cooldown limit curves. APPLICABILITY: At all times. . ACTION: ' 7 On{ }&Ylb ' b With any of tie above limif.s exceeded, restore the temperature and/or pressure O to within the limit withiri 30 minutes; perfom an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity ) I of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation or be in at least HOT STANDBY within the ' next 6 hours and reduce the RCS T ,yg and pressure to less than 200*F and
]DOpsig,respectively,withinthefollowing30 hours.
)
' SURVEILLANCE REQUIREMENTS
- SR 3.3.3,1 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be
~
determined to be within the limits at least once per 30 minutas during system heatup ooldown, and inservice leak an( hydrostatic" tasting operations. . 6FThe& LCO ,)W,ti"taf/On J. 2. reactorEvessel S S material L-- )e. ! 7 . 4(. 9.2 irradiation sur. <illance ve specimens j shall be removed and examined, to determine changes in material properties, j as required by 10 CFR Part 50, Appendix H, in accordance with the schedule . in Table 4.4-5. The results of these examinations shall be used to update - l gigures3.4-2and3.4-3. l l r
i l
] COMANCHE PEAK - UNIT 1 3/4 4-32 i
_.._______________a
'1 j
)
E cket No. 50-445 August 14. JM7 1 i 3 , 1 i
.bO hib, b .
FIGURE 3.4-2 : k REACTOR COOLANT SYSTEM HEATUP LIMITATIONS - APPLICABLE UP TO EFPY r 1 If I
] COMANCHE PEAK - UNIT 1 3/4 4-33
)
'Booket Glo. 50-445 l Ansgust 14, 1987 l O .
I n i
)
0 . 1 k4 i 1 4 LCo 3,3,3 : FIGURE 3.4-3 l REACTOR C30LANT SYSTEM COOLDOWN LIMITATIONS - APPLICABLE UP TO- EFPY ~{ s MCOMANCHEPEAK-UNIT 1 3/4 4-34
I Booket Ilo. 50-445 g August 14, 1987 ' cs . i d l Do ucua nr TCD 3,3.3 jo05 c4wn # 2. . r , o 1
\ s $
I g t-y, 1 J W !
$ % ,/
= s' 1 E 5 -
t i . 2 e e
~
x I N - e 4 5 1
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i d
- mE E SG i m
a ug 5
- 1 e . ,
p
.W 5 A v ==
1 y 1
$b- ; ,s ::
I. OE
./ COMANCHE PIAX - UNIT 1 3/4 4-35 l
____________ _ m
I i r E ~ fhV i O t 7
! REACTOR COOLANT SYSTEM PRESSURI2ER I
LIMITING CONDITION FOR OPERATION i 3.4.9.2 The pressurizer temperature shall be limited to: j
- a. A maximum heatup of {1003*F in avy 1-hour period. <
- b. A maximum cooldown of [200]*F in any 1-hour period, and ]
- c. A maximum spray ester temperature alifferential of [320]*F. j APPLICABILITY: At all times. J l
i ACTION: With the pressurizer temperature liwits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition ! on the structural integrity of the pressurizer; determine that the pressurizer j temnins acceptable for continued operation or be in at least NOT STANDBY within the next 6 hours and reduce the pressurizer pressure to less than 500 psig 4 within the following 30 hours.
\' .
1 1 SURVEILLANCE REQUIREMENTS 4.4.9.2 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes durin0 system heatap or can1down. - The j
, spray water hy...i.ure diff.....i.ial shall be determined to be 'within the 1 limit at least once per 12 hours during auxiliary spray operation.
4 I , e* e COMANCHE PEAK - UNIT 1 3/4 4-36 i
1 i Socket No. 50-445
.3, 3 August 14, 1987 REACTOR COOLANT SYSTEM
- 3.3.1%
OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 1
~
I
. a 3.4.9.3 At least one of the following Overpressure Protection Systems shall j
,,dC S 3,l3 b '
- a. Two power-operated relief valves (PORVs) with a lift setting of less than or 1 to I4503 psig, or
' L60 Si3,1 .
3 i
- b. . The Reactor Coolant System (RCS) depressurized with an RCS went of greater than.or equal to aquare inches.
' APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is less than i or equal to [275)'F, MODE 5 and MODE 6 with the reactor Wessel head an. !
ACTION: ( I 1 h b LCnl.IIIH1b r) l
- 4. With one PORV inoperab$e, restore the inoperable pDRV to UPERABLE j status within 7 days or' depressurize and went the RCS through at i least a,, squ re inch vent within the next 8 hours.
' ~' Wi both PO Vs. inoperable, depressurize and went the RCS through at i les ai square inch went ithin { urs 1 L D(, (,(( ?6r 1.CO Se3,I j)ASTs CM10H M [ ' In e event either the PORVs or the RCS vent (s) are used to mitigate {c. an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circaustances initiating the 1 tra'isient, the effect of the PORVs or RCS vent (s) on the transient, (
+
% , .v - .any cgrrective Actien, . ., ta provant recurrence.
- 1. J 1. 0"E Tc' f,
- d. provisions 9P7iLft38la,N of Specification 3.0.4 am not applicable. I 1
l e e e COMANCHE PEAK - UNIT 1 3/4 4-37
I I REACTOR COOLANT SYSTEM Socket No. 50-445 August 14, 1987 l d OVERPRESSURE PROTECTION SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by . b k 3. 3,13,8 I (
- a. Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days .f prior to entering a cpndition in which the PORV is required OPERABLE l i and at least once per 31 days thereafter when the PDRV is required -
~
, be b
- b. Performance of a CHANNEL CALIBRATION en the P0tV actuation channel j at 18 months; and '
S eastonc0,pe5 b,5. Pc. Ver fying the PORV isolation valve is spen at least once per 72 hours when the PORV is being used for svarpressure protection. l
- sR 3 3, & 3 I 4.4.9.3.2 The RC5 vent (s) shall be verified to be open at least ence per . )
12 hours" when the vent (s) is being used for everpressura protection. ! I (/ . i, "Except when the vent pathway is provided with a valve which is locked, sealed. ' or otherwise secured in the open position, then verify these valves open at i anst anca per 31 days. 4 ( I 4 e i COMANCHE PEAK - UNIT 1 3/4 4-38
ReicS or to.Ae t ' S ea to Ae 17. 445 REACTOR CDOLANT SYSTEM h 7 3/4.4.10 STRUCTURAL INTEGRITY i l LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class I, 2, and 3 components shall be maintained in accordance with Specification 4.4.10. 1 APPLICABILITY: All MODES. ACTION:
- a. ' With the structural integrity of any ASME Code Class 1 component (s) <
not conforming to the above requirements, restore the structural
' integrity 'of the affected component (s) to within its limit or isolate the affected component (s) 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 (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolete the affected component (s) prior to increasing the Reactor Coolant D System temperature above 2D0*F.
N) 4
- c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.
- d. The provisions of Specification 3.D.4 are not applicable.
StIRVEI11AMCE REQUIREMENTS d 5.. toc h 17 4.4.10 In addition to the requituments of Specification 4.0.5, ecch reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1. Aug'ust 1975. i
/
1 COMANCHE PEAK - Uh*T 1 3/4 4-39 _ _ _ _ _ _ _ - _ - l
# (/ O blL & l tooket tio. 50-445 REACTOR COOLANT SYSTEM ; August l14, 1987 h\
3/4.4.11 REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 At least one Reactor Coolant System vant path consisting of [two) vent l valves (s) and [one) block valve powered from emergency busses shall be OPERABLE' and closed at each of the following locations: ,
- a. [ Reactor vessel head),
- b. { Pressurizer steam space), and
- c. [ Reactor Coolant System high point).
APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:
- a. With one of the above Reacter Coolant System vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable ,
vent path is maintained c1csed with power temoved from the valve actuator of all the vent valves and block valves in the inoperable vent pat' " etore the inoperable vent path to OPERABLE status 1 6 within ~d ,, or, be in NOT STANDBY within 6 hours and in COLD SHLuc .ithin the following 30 hours.
- b. With two or more Reactor Coolant System vent paths' inoperable; maintain the inoperable vent path closed with power removed from the valve actuators of all the vent valves and block valves in the inoperable vent paths, and restore at least [two) of the vent :
~
paths to OPERABLE status within 72 hours or be in HOT STANDBY l
. .within 6 hours and in COLD SHUTDOWN.within the following E hours. - g q
SURVEILLANCE REQUIREMENTS d 4.4.11.1 Each Reactor Coolant System vent path black ~vaiva mot required to 1 U be closed by ACTION a. or b.s above, shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one completa cycle of full ., l travel from the control room.
~ 4.4.11.2 Each Reactor Coolant System vent path shall be demonstrated j OPERABLE at least once per 18 months by: !j
- a. Verifying all manual isolation valves'in each vent path are locked ;
in the open position, i
- b. Cycling each vent valve through at least one complete cycle of C full travel from the control room, and 1
- c. Verifying flow through the Reactor Coolant System vent paths-during venting.
COMANCHE PEAK - UNIT 1 3/4 4-40
i EMERGENCY CORE COOLING SYSTEMS , i' 3/4.5.1 ACCUMULATORS l COLD LEG INJECTION . LIMITING CONDITION FOR OPERATION j l
- L eo *b % i 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with: >
- a. The discharge isolation valve open with power removed, l 1
- b. A contained borated water volume of between 17853) and 18171) gallons, j
- c. A boron concentration of between [1900) and [2100] ppe, and f
- d. A nitrogen cover pressure of between [385] and 14813 psig.
j APPLICABILITY: MODES 1, 2, and 3*. , j ACTION: 1 0-c w L motJb bM C
- a. [With one cold leg injection accumulator inoperable, except as a result of a closed isolation valve, restore the inoperable accumulator to I
OPERABLE status within 1 hour or be in at least HOT STANDBY within ; the next 6 hours and reduce pressurizer pressure to less than 1000 psig within the following 6 hours. .
- b. dith one cold leg injection accumulator inoperable due to the 1 isolation valve being closed, either immediately open the isolation !
<alve or be in at least HOT STANDBY within 6 hours and reduce
. stessurizer pressure to less than 1000 psis within the following )
5 hours. Si1RVEILLANCE REQUIREMENTS 4.5.1.111 Each cold leg injection accumulator shall be demonstrated-DPERABLE:
- a. . At least once per 12 hours by:
3 % \.'7-
- 1) (Verifying,55y <the absence of alarms, the contained borated water volumje and1hitronen cover-pressure in the tanks 1 and S fL 3 6 .1.1 ""**"0
- 2) Terifying that each cold leg injection accumulator isolation dalve is open.
" Pressurizer pressure above 1000 psig.
CDMANCHE PEAK - UNIT 1 3/4 5-1
i i EMERGENCY CORE COOLING SYSTEMS. Socket l August;No. 50 445 14, 1987
! SURVEILLANCE REQUIREMENTS (Continued) l 5 tt 3 9 1 W 'i
- b. At least once per 31 days and within 6 hours after each solution vol- )'
use increase of greater than or equal to [1% of tank volume) by veri-fying the boron concentration of the solution in the water-filled ) m;cumulator; j S R 3. 4 1 X i
- c. "Kt least once per 31 days when the RCS pressure is above 1000 psig by verifying that power to the isolation valve operator is .. disconnected ' i
,_by removal. of the breaker from the circuit. j
. De t e %.t p.v- Tashhwb n c.D 1 4.8 t4 em Il a
- d. At least once per 18 months by verifying tilet each accumulator ~ isola- 1 tion valve. opens automatically under each af the following. conditions- !
- 1) When an actual or a .simuhted RCS pressum signal arr==* the ]
P-11 (Pressurizer Pressure Block af Safety Injection) Jetpoint. .i and
]
Q Upon receipt of a Safety Injection test pl. 4.5.1.1.2 Each Delebt e v- JuhR accumulator b andt. pressurd waterTevel r.o 5. % t 13-channel shall be demon-strated DPIRABLE: (~ a. At least once per 31 days be the performance of an ANALIX1 CHANNEL OPERATIONAL TEST, and-
- b. At least once per IB months by the performance of a CHANNEL CALIBRATION. ,
1 l h' 1
.- s
.I
.q H
e
- w. sg.
COMANCHE PEAK - UNIT 1 3/4 5-2
i EMERGENCY CORE C00l!NG SYSTEMS [ 5 j
~(
UPPER HEAD INJECTION
-Nob he l., cA<A g Mt s. m Rey.~ 5. M # * ,
j l _ LIMITING CONDITION FOR OPERATION ! 3.5.1.2 Each Upper Head Injection Accumulator System shall be OPERABLE with:
]
- a. The isolation valves open, .J
- b. The water-filled accumulator containing a minimum of [18503 cubic feet of borated water having a boron concentration of between 11900]
and [2100j ppe, and :i
- c. The nitrogen-bearing accumulator pssurized to between and psig. ;
APPLICABILITY: MODES 1, 2, and 3". l ACTION: .
~
a, ' With the Upper Head Injection Accumulator System inoperable, except as a result.of a closed isolation valve (s), restore the Upper Head ; Injection Accumulator System to OPERABLE status within 1 hour or be l in at least HOT STANDBY within the next 6 hours and reduce pressurizer ' k pressure to less than 1900 psig within the following 6 hours.
- b. With the Upper Head Injection Accumulator System inoperable due to the isolation valve (s) being closed, either immediately open the isolation valve (s) or be in at least HOT STANDBY within 6 hours and reduce pressurizer pressure to less than 1900 psig within the following 6 hours.
i SURVEILtRWCE ltEUb m mEdiS
'4.5.1~.2 Esch Upper Head Injection Accumulator System shall be tismonstrated a
DPERABLE:
- a. At least once per 12 hours by:
- 1) Verifying the containment borated water volume and nitrogen pressure in an accumulator, and
- 2) Verifying that each accumulator isolation valve is open.
" Pressurizer pressure above 1900 psig.
k COMANCHE PEAK - UNIT 1 3/4 5-3 _________________.____-__________w
todet Wo. 50-445 August 14. 1987 i.OEMERGENCYCORECOOLINGSYSTEMS Nd EduM sA N ERi% (. s- e Nog B SURVEILLANCE REQUIREMENTS (Continued)
- b. At least once per 31 dayi and within 6 hours after each solution volume increase of greater than or equal to [1% of tank volume) by verifying the baron concentration of the solution in the water-filled accumulator;
- c. At least once per 18 sonths by:
- 1) Verifying that each accumulator isolation valve closes automati-cally when the water level in the accumulator is [93.212.7 inches] above the working line on the water-filled accumulator, and
- 2) Verifying that the tota 1' dissolved nitrogen and airin the water-filled accumulators is less than [803 scf w [18DD] cubic feet.cf water.
- d. At least once per 5 years and if the requirements if Specifiestion 4.5.1.2c.2) are not met, by replacing the membrane installed between the water-filled and nitrogen-bearing accumulators.
~
W e 4 0I O* CDMANCHE PEAK - UNIT 1 3/4 5-4 .
E j So det glo. 50 445 EMERGENCY CORE COOLING SYSTEMS
/ August 14, .198f ,
J 3/4.5.2 ECCS SUB5YSTEMS - T,g GREATER THAN OR EQUAL TO 350'F-
-LIMITING C3NDITION FOR OPERATION q
-l
~
Leo 3.91 3.5.2 Two independent Emergency Com Cooling System (ECCS) sesystems shall be OPERABLE with each subsystem comprised af: -!
- a. One DPERABLE centrifugal charging pum'p, -
- b. Dne DPERABLE Safety Injection pump (four loop plants'ionly),
- c. One DPERABLE RHR heat exchanger, )
. d. Dne DPERABLE RHR pump, and
- e. An DPERABLE flow path capable of taking suction feathe virtueling water storage tank on.a Safety _ Injection signal and automatically transferring suction to the cant &fnment susp sluring the recirculation phase of operation.
APPLICABILITY: MODES 1, 2, 'and 3. j 1 I ACTION: , Cous m.u b -
- a. Yth one ECCS subsystem inoperable, resten the inoperable subsystem to OPERABLE status within 72 hours or be in at least HDT STANDBY within the next 6 hours and in HDT SHUTDOWN within the fallowing 6 hours. -
0,%M ms4< >cAe A 4. Move +o S.tg . 2
~
- b. Tn the elent the ECCS is actuated and injects waterinto the Reactor Coolant Systas, a Special Report shall'be prepared and submitted to f the Commission pursuant to Specification"$;9.2 withip'90 days describ- i o
ing the circumstances of the actuation and the total accumulated actuation cycles to date. The curmnt value of the usage factor j
^
for each affected Safety injection nozzle shall be provided in this i pecial Report whenever its value exceeds'0.70. C k i I 3
)
4 l
/COMANCHF PEAK - UNIT 1 3/4 5-5 l
Met 96o. 50-445 l
- EMERGENCY CORE COOLING SYSTEMS Ansgust 14, 1987
' 3 SURVE3LLANCE REQUIREMENTS I
4.5.2 Each ECC5 subsystem shall be demonstrated OPERABLE: sR $.t.t )
- a. Tt'1 east once per 12 hours by verifying that the following valves 1 are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position j 4h j
- b. Atleastoncepr31daysby: '
- 2) YerNyikg hat the ECCS piping is fuil of water ty venting the i
ECCS pump casings and accessible discharge piping Afgh points, , and ) 3 R 3.M.2 3 "
- 2) Terifying that each valve (manuel, power operated, wr automatic) in the flow path that is not locked, sealed, or otherwise secured in positio , is in its correct position.
- c. 'By bv'IsIai [nYpe di'on' ic N erifN s N t'no Ioo $ debris (rags, trash, clothing, etc.) is present in the containment which could be ,
transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
- 1) For all accessible areas of the containment prior to attablish- ,
ing CONTAINMENT INTEGRITY, and l
- 2) Of the areas affectad within containment at the completion of l each containment entry when CONTAIWiENT INTEGRITY is established.
- d. - At least once per 18 samths try:
- 3) Terdkng'Nm'atic 3
isolation and interlock action of the RHR system from the Reacter Coolant System to ensure that: ; a) With a simulated or actual Reactor Coolant System pressure signal greater than or equal to [4253 psig the interlocks prevent the valves from being opened, and
. b) With a simulated or actual Reactor Coolant System pressure
- signal less than or equal to [750] psig the interlocks will
~
cause the valves to avtamatically close.
- 2) TvfsYaNsfeYtNohtTeYonNnNnYsdaYv'erifyingthat the subsystem suction inlets are not r'estricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress cr abnormal corrosion.
/ COMANCHE PEAK - UNIT 1 3/4 5-6
EMERGENCY L.QTOLING SYSTEMS Sooket Ilo. 50-445 August ~ 14, 1987 l (' SURVEILLANCE REQUIREMENTS (Continued)
- e. At least'once per 18 months, during shutdown, by:
s 3 g.2..T
- 1) verify'ing that each automatic valve in the flow path actuates to its correct position on (Safety Injection actuation and Automatic Switchover to Containment Stuap) test signals, and
! 5 R. 3 4 2."1
- 2) Terifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:
I a) Centrifugal charging pump. I L b) Safety Injection pump, and c) RHR pump. st u .2 s
- f. By verffying that each of the following pumps develops the indicated differential pressure on recirculation flow when testad pdrsuant to Specification 4.0.5: ,
- 1) Centrifugal charging pump > psid,
- 2) Safety Injection pump > psid, and
- 3) RHR pump > P5id- l g.
%positionstopforthefollowingECCSthrottlevalves:Nri}y M he
-Within p a \e4khours
,L p w LCo s. \.t &s% esr A~ s he - t \ .
following completion of eac$ valve stroking 4
- 1) l operation er maintenance on the valve when theICCS subsysiams l j are required to he SPDAB11, and ;
- 2) 'At 1 east once per 18 months.
HP51 System ' l. PSI System i Valve Number _ Valve Number i l i IC0KANCHE PEAK - UNIT 1 3/4 5-7
l EMERGENCY CORE COOLING SYSTEMS Socket No. 50-445 August 14, 1987 'i O SURVEILLANCE REQUIREMENTS (Continued) _5 R 3. % 2 . fr .
- h. By performing a flow balance test, during shutdown, following com-pletion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
- 1) For centrifugal charging pump lines, with a single pump running:
a) The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to gpm, and b) The total pump flow rate is less than or equal to gpm.
- 2) For Safety Injection pump lines, with a single pump running:
a) The sum of the injection line flow rates, excluding the highest flow rate, is greater than er equal to gps, and b) The total pump flow rate is less than er equal to gpm. -
- 3) For RHR pump lines, with a single pump running, the sum of the injection line . flow rates is greater than or equal to gpm.
. 3 l
T O
\
M CO MANCHE PEAK - UNIT 1 3/4 5-8
I EMERGENCY CORE COOLING SYSTEMS l
- l. 3/4.5.3 ECCS SUBSYSTEMS - T,y LESS THAN 350'F LIMITING CONDITION FOR OPERATION l
Leo 3, % .3 - 3.5.3 As a minimum, one ECC5 aubsystem comprised of the follodng shall be DPERABLE:
- a. One OPERABLE centrifugal charging pump.*
- b. ~ One DPERABLE RHR heat exchanger,
- c. Dne DPIRABLE RHR pump, and l l
- d. An DPERABLE flow path capable of taking suction from ttie tufneling . !
water storage tank upon being manually realigned and transferring -i suction to the containment sump during the recirculation phase of 1 operation. - APPLICABILITY: MODE 4. ; i ACTION: l _ cow >cnce A 4 a. With no ECCS subsystem DPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from'the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within I hour er be in COLD SHUTDOWN within the next 10 hours. couscrve B -
- b. ,~Gith no ECCS subsystem DPERABLE because of the inoperability of either the residual heat removal heat exchanger or RHR pump, restore
., at least one ECCS subsystem to GERABLE status or maintain the Raac-
" '" P ter Coolant System T,,, has thma 250*F by use of alternate heat Ismoval methods.
+p,% mvrri> N 4 M*C b S 4 '-
' r." n the evknt the ECCS is actuated andinjects water into the Reactor Coolant System, a~ Special Report sha11'be prepared and submitted to the Commission pursuant to Specification 6.9 4 within 90 drys describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected Safety Injection antzle shall be provided in this
. Special Report whenever its value exceeds D.70.
Pp h
" A maximum N e c W N ugb cha king u and 6,, 5 e njection pump t shall be OPERABLE whenever the temperature of one or more of the RCS cold
< 1egs is less than or equal to [275)*F.
/ COMANCHE PEAK - UNIT 1 3/4 5-9
I i EMERGENCY CORE COOLING SYSTEMS Booket tio. 50-445 ) August 14, 1987 4 [ k SURVEILLANCE REQUIREMENTS i 5fL 3. % 3 .\ 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable requirements of Specification 4.5.2. . L 3R 3 .3, g g , g f 4.5.3.2 All charging pumps and Safety Injection pumps, er. cept the above re- { quired OPERABLE pumps, shall be demonstrated inoperable by verifying that the i motor circuit breakers are secured in the open position at least once per ] 12 hours whenever the temperature of one er more of the ACS r.cid legs is less than or equal to 12753*F. l l l l l
- )
i j H I
.i e *
.e
/COMANCHEPEAK-UNIT 1 3/4 5-10
l 1 3/4.5.4 BORON INJECTION SYSTEM Docket No. 50-445 August 14, E987 [ i {~
,s BORON INJECTION TANK [0PTIONAL IF NOT TAKEN CREDIT FOR IN PLANT SPECIFIC
- ANALYSES) ,
LIMITING CONDITION FOR OPERATION Leo 3. % 3.5.4.1 The boron injection tank shall be DPERABLE with: and I
- a. A contained borated water voltrae of between gallons,
- b. A boron concentration of between 20,000 and 22,50D ppa, and
- c. .A minimum.. solution temperature of 145'F. j
( APPLICABILITY: MODES 1, 2, and J. j 1 ACTION: ' to wp m ew A /B /C With the boron, injection tank inoperable, restore the tank to WNBE status l vithin I hourAr be in HOT STANDBY and borated to a SHUTDDWN MARGIN equivalent to 1% Wk/k at 200*F within the next 6 hours;jtestore the tank to DPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 12 hours. , SURVEILLANCE REQUIREMENTS 4.5.4.1 The boren injection tank shall be demonstrated DPERABLE by: 1 itt. 3. % .2
- a. I Verifying'the contained borated water solame at least once per 7 days,
_5R u. 3
- b. - Veri fy~,ing the . boron enncentration of the unter in the tank at least
.JtDee Per 7 days, .and t
3%. 3 . H. to , \
- c. perifyingthewatertemperatureatleastonceMr24 hours.
i e l 40MANCHE PEAK - UNIT 1 3/4 5-11
Becket tio. 50-445 BORON INJECTION SYSTEM Ansgust 14, 1987 HEAT TRAZING _ R s Ic.c A l o ds1 ME MD p e r- No k- I-LIMITING CONDITION FOR OPERATION 3.5.4.2 At least two independent channels of heat tracing shall be DPERABLE for the boron injection tank and for the heat traced portions of the associ-ated flow paths. APPLICABILITY: MODES 1, 2, and 3. ACTION: With only one channel of heat tracing on either the boron injection tank or en the heat traced portion of an associated flow path OPERABLE, operation may continue for up to 30 days provided the tank and flow path temperatures are verified to be greater than or equal to [145]*F at least once per 8 hours; otherwise, be in at least HOT STANDBY within 5 hours and in HDT.5HUTDOWN within the following 6 hours. - t k . SURVEILLANCE REQUIREMENTS
.4.5.4.2 Each heat tracing channel for the borna injection tank and associated flow path shall ha demonstrated DPERABLE:
- a. At least ance per 31 days by energizing mach heat tracing thannel,
.and
- b. At least once per 24 hoers by wilfying the tank and flow path
' temperatures to be greater than or equal to [1453*F. The tank temperature shall be detemined by measurement. The flow path temperature shall be determined by either measurement or recircula-tien flow until establishment of equilibrium temperatures within the tank. ;
COMANCHE PEAK - UNIT 1 3/4 5-12
BORON INJECTION SYSTEM Docket elo. 60-445
* . August 14, 1987 ik 3/4.5.5 REFUELING WATER STORAGE TANK 1
LIMITING CONDITION FOR OPERATION J LCO 3,9 5 l
'3.5.5 The refueling water storage tank (RWST) shall be OPERABLE with: .
- a. A minimum contained borated water volume of gallons. !
l
- b. A baron concentration of between [2000] and I2200J ppe af baron.
- c. .A minimum solution temperature of [35]'F, and r 1
- d. A maximum solution temperature of [100]'F. l APPLICABILITY: MODES 1, 2, 3 and 4. !
ACTION: ' Co mmee 6A5 - With the RW5T inoperable, restore the tank to DPERABLE status wittiin I hour or l be in at least HOT STANDBY within 6 hours and in COLD . SHUTDOWN withia the following 30 hours.
. i l
I i SURVEILLANCE REQUIREMENTS
> 4.5.5 The ehtST_shall to.alemenstrated DPERABLE: ;
- a. ~ At least once per 7 days by:
_. S R 3 . % . S. t ,
- 1) Verifying the contained berated unter volume _in the . tank.. and !
- 2) derihyfnkhoron concentrattom of the water.
5 R 3.%.S 3 l b' . At least once per 24 hours by verifying the RWST temperature when the [outside) air temperature is less than [35]'F er greater than (100)*F. k
'/COMANCHEPEAK-UNIT 1 3/4 5-13
I Socket NW. 50-(45 August 14, 1987 SECTION 3/4 6A . CONTAINMENT SYSTEMS SPICIFICATIDNS FOR WESTINGHOUSE ATMOSPHERIC TYPE CONTAINMENT [ O . a S W e D V COMANCHE PEAK - UNIT 1 3/4 6-0A s
Socket.No. 50-445 3/4.6' CONTAINMENT SYSTEMS August-14,-1987 j,Os 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION
/C0 3.!~]
- 3. 6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3, and 4. C Q U b / T i 0 K /5 Q c., d E . f. Without primary CONTAINMENT INTEGRITY, vestore CONTAINMENT INTEGRITY within 1 hour or_ be in at least NOT STANDBY within the next 6 hours and la 'CDLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated: gB)a. . S;/. /At least once per 31 days by verifying that all penetrations
- not E.
capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Tabla 3.5-1 of Specification 3.6.4.1;
, v 2 3. By n t. At 3R 2 5;/.f(See Alek1 verifyfrg that each containme)nt air lock is in compliance with
. the requirements of Specification 3.5.1.3; and 2* M/.GRiotW.kh ,e-tr. tion 3.ct so,y,e 2.st*,, ,
a except:the containment air locks, if spened following a Type A or B
- test, by leak rate testing the seal with gas at a irressure not less than P , [50 psigh and verifying that when the seasured leakage rata for thlse seals'is added to the-leakage rates detemined pursuant to ;
Specification 4.6.1.2d. for all ather Type 8 and C penetrations, the codined leakage rate is less than 0.50 L ,. SR 3.r. /. 3 TExcept valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during ea m COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days. N [ CDMANCHE PEAK - UNIT 1 3/4 6-IA
1 Socket No. 50-445 CONTAINMENT SYSTEMS August 14, 1987 OCONTAINMENTLEAKAGE % :. c.t. r (se-c Alde . (J<e-Alde5), LIMITING CONDITION FOR OPERATION. - 3.6.1.2 Containment leakage rates shall'be limited to: ,
- s. An overall integrated leakage rate of: ;
- 1) Less than or equal to L,,10.203% by weight of the corttainment air per 24 hours at P,, [50 psig], or
.2) Less then or equal to Lg, [0.14]E by weight af the containment air per 24 hours at a reduced pressure af tp , I25 psig].
- b. A combined leakage rate of less than D.6D L, for all penetrations and valves subject to Type 8 and C tests, when pressurized to P ,.
APPLICABILITY: MODES 1, 2, 3 and 4. . ACTION: g With either the measured overall integrated containment leakage Tate exceeding ( 0.75 L, or 0.75 L g, as applicable, or the esasured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L,, restore the overall integrated leakage rate to less' than 0.75 L, or less than 0.75 L , as applicable, and the combined leakage rate for all penetrations t
. subject to Type B and C tests to less than 0.60 L, prior to increasing the Reactor Coolant System temperature above 200'F. 1 SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates'shall beltemonstrpted at the following test schedule and shall be determined in conformance with the' criteria speci- ;
fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-[1972):
- a. Three Type A tests ~(Overall Integrated Containment Leakege Rate) shall be conducted at 40 t 10 month intervals during shutdown at a pressure not less than either P,, [50 psig], or at Pg. [25 psig),
during each 10 year service period. The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection; [COMANCHEPEAK-UNIT 1 3/4 6-2A
i CONTAINMENT SYSTEMS ' Docket tio. 60-445 R3,r.j.5"(c.ntkucL) SURVEILLANCE REQUIREMENTS (Continued)
- b. If any periodic Type A test fails to meet either 0.75 L, or 0.75 Lg, the test' schedule for subsequent Type A tests shall be reviewed and
' approved by the Commissica. If two consecutive Type A tests fail to.
meet either 0.75 L, or 0.75 Lg, a Type A test shall be performed at 1 least every 18 months until two consecutive Type A tests meet either 0.75 L, or 0.75 Lt at which time the above test schedule may be J resumed;
- c. The accuracy of each Type A test shall be verified by a supplemental test which: 1 i
- 1) Confirms the accuracy of the test by verifying that the supple-mental test result, L g, is in accordance with the appropriate following equation:
1Lg- (L, + L,) 1 10.25 La or 1 L,- (Lta
- l )o 1 $ D.25 Ig where L,, or L g, is the measured Type A test leakage and 1, '
is the superimposed leak; 1 2) Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test; and j i
- 3) Requires that the rate at which gas is injected into the contain- )
ment or bled from the containment during the supplemental test i is between 0.75 L, and 1.25 L,; or 0.75 Lg and 1.25 Lg. 1
- d. Type 8 and C tests shall be conducted with gas at a pressure not !
6 . 2,-less than P,, [50 psig], at datervals me granter.than 24. months except for tests involving:
- 1) Air locks,
- 2) ' Purge supply and exhaust' isolation valves with resilient material 1 seals. .
- 3) Penetrations using continuous Lankage Monitoring Systems, and
- 4) Valves pressurized with fluid from a Seal Systes,
- e. Air locks shall be tested and demonstrated 0PERABLE by the require- ,
ments of Specification 4.6.1.3; n f. Purge supply and exhaust isolation valves with resilient material
; seals shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.8.3 or 4.6.1.8.4, as applicable; OMANCHE PEAK - UNIT 1 3/4 6-3A
Socket Wo. 50-445 CONTAINMENT SYSTEMS August I4,1987 l SURVEILLANCE REQUIREMENTS (Continued)
'
- 3 S~. i. r (ce-,s wd) \
l g. Type B periodic tests are not-required for penetrations continuously sonitored by the Containment Isolation Valve and Channel Weld Pressur-ization Systems provided the systems are DFERABLE by the require-ments of Specification 4.6.1.4; i j
- h. Leakage from isolation valves that are sealed with fluid from a Seal j l System may be excluded, subject to the provisions of Appendix J, Section III.C.3, when determining the combined leakage rata provided l l
the Seal System and valves are pressurized to at least 1.1D P,, [55 l j psig], and the seal system capacity is adequata to urintain system pressure for at least 30 days, . i i 1. Type B tests for penetrations employing a continuous Lankage j j Monitoring System shall be conducted at P,, ISD psis], at intervals no ' greater than crce per 3 years; and
- j. The provisions of Specification 4.D.2 are not applicable.
~
4 S e t OMANCHE PEAK - UNIT 1 3/4 6-4A
CONTAINMENT SYSTEMS Socket No. 50-445 CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION i 3.6.1.3 Each containment air lock shall be DPERABLE with: Cb- ' ' Ja.DEF//Jrrio Both doors An closed
~ c.wryNMEN except when Y CNTECNTybe.Kfinu,d the air lock is ing use for normal
' transit entry and exit through the containment, then at least one air lock door shall be closed, and iT3.r:17 b. (See air An overall /%+e.- lock la8kage rate of less than er equal to D.D51, at P ,, [50] psig. g APPL 1hBILITY: MDDES 1, 2, 3 and 4. ACTION: L&C }. f f whit'ONS $. A d E.'
- a. With one containment air lock door inoperable:
Maintain at least the OPERABLE air lock door closed and either
- 1. '
restore the inoperable air lock door to OPERABLE status within 24 hours or lock the OPERABLE air inck door closed;
- 2. Operation may then continue until performance of the next 4
required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days;
- 3. Otherwise, be in at least HDT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours; and -
- 4. The 1rrorisions of Specification 3.0.4 are not applicable.
4.c0the C With 3. containment C / countriost:r c. air l. en.d. E.ock' inoperable, except as the tesulttf an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours _or be in at least HDT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. ,. i t. - ..c y c. r 4 e , w. O
/COMANCHEPEAK-UNIT 1 3/4 6-5A
CONTAINMENT SYSTEMS Docket tio. 50-445 August 14, 1987
.OSURVEILLANCEREQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
w Sit 3.: K /. T72(5hours Within e.L N e -fe. Y following) each closing, except when the air lock is ' c. being used for multiple entries, then at least once per 72 hours, by verifying seal leakage flow measurements whenismeasured less thanfor[0.01) L,[as at least 30] determined seconds with bytheprecision volume between the seals at a constant pressura of [50 psig];
- b. By conducting overall air lock leakage tests at not less than P,,
[50 psig], and verifying the overall air lock leakage Tata is within its limit: .
~
! 1) At least once per 6 months',* and 4
- 2) Prior to establishing CONTAltMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.** .
"N 3. M i. 4
- c. At least once per 6 months by verifying that only wne door in each air lock can be opened at a time.
n k
~
]
I o
,1 1
i TR 3. Y t.r (se Atere. v.)
"The provisions of Specification 4.0.2 are not applicable.
**This represents an exemption to Appendix J, paragraph III.D.2 of 10 CFR Part 50.
4 , [ Applicant must request this exemption.) 0MANCHE PEAK - UNIT 1 3/4 6-6A
. Socket No. 50-445 CONTAINMENT SYSTEMS August 14,'1987 CONTAINMENT ISOLATION VALVE AND CHANNEL WELD PRESSURIZATION SYSTEMS l 75 ^ . T./. 7 (S&e Nefe T)
LIMITING CONDITION FOR OPERATION 3.6.1.4 The Containment Isolation Valve and Channel Wald Pressurization - 1 Systems shall be OPERABLE. . APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: With the Containment Isolation Valve or Channel Wald Pressurization System - inoperable, restore the inoperable system to DPERABLE status within 7 days or be in at least HOT STANDBY within the next 4 hours and in CDiB 54RITDOWN within ) i {thefollowing30 hours. _ i I k lSURVEILLANCEREQUIREMENTS l 4.6.1.4.1 The Containment Isolation Valve Pressurization System shall be demonstrated OPERABLE at least once per 31 days by verifying that the system
. is pressurized to greater than or aquel to 1.10 P , [55 psig], and has adequate capacity to maintain system pressure for at least,30 days.
4.5.1.4.2 "The Containment thanneliteWPressurtzstion System shall be demon- l strated OPERABLE at least once per 31 days by verifying that the system is pressurized to greater:than or equal to P,..[50 psig], and has adequate capacity to amistain system pressure for at'least 30 adays. m-I vt0MANCHE PEAK - UNIT 1 3/4 6-7A
Docket Woe 50-445 CONTAINMENT SYSTEMS August 14, 1987 7 INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION ) LC D 3 6 17. ( Al 3.6.1.5 Primary containment internal pressure shall be maintained between ! and psig. APPLICABILITY: MODES 1, 2, 3, and 4. J ACTION: c.c u Di rte o A u B With the. containment internal pressure outside of the limits above, restore the internal prussure to within the limits within 1 hour or be in at least HOT 1 STANDBY within the next 6 hours and in COLD SHUIDOWN within the following 30 j
. ttours.
i l I
~
l 1
~
k , SURVEILLANCE REQUIREMENTS SR. 3. S ,12. t UO
- 4.5.1.5 The primary containment internal pmssam shall he Jtetemined to be within the limits at least once per 12 hours. (
I l
/COMANCHEPEAK-UNIT 1 3/4 6-BA
l CONTAINMENT SYSTEMS Socket tio. 50-445 August 14, 1987 ! AIR TEMPERATURE ( LIMITING CONDITION FOR OPERATION L.CC 3. Sin LN i
' F.
3.6.1.6 Primary containment average air temperature shall not exceed APPLICABILITY: MODES 1, 2, 3, and 4. I J ACTION: I 00pptreo A4E *F,veduce the With the containment average air temperature greater t.han average air temperature to within the limit within 8 hours, or be in at least i HOT STAND 8Y within the next S hours .and in COLD SHUTDOWN within the following 3D bours. u SURVEILLANCE REQUIREMENTS
- S L ~$ . 9 M 'l LBb 4.6.1.6 The primary containment everage air temperature shall be the arith-metical average of the temperatures at the following locations and shall be determined at least once per 24 hours:
1 3.T.G LT) d incation . Mo v._,L % B ase) .
- a. 1 b.,
N 4 c. l d. e. [COMANCHEPEAK-UNIT 1 3/4 6-9A
Docket No. 50-445 CONTAINMENT SYSTEMS August:14, 1987 CONTAINMENT STRUCTURAL INTEGRITY [ Prestressed concrete containment with ungrouted tencons and typical come.] LIMITING CONDITION FOR OPERATION Re b::cdeid 4sv4.o TEcl~ s pec.s -t.\ 3.6.1.7 The structu al integrity of the contain(m ent s c.c_ shal eNe maintai(n$ce ed at a t&k I'd level consistent with the acceptance critaria in Specification 4.6.1.7. APPLICABILITY: MODES 1, 2, 3, and 4. - ACTION:
- a. With more than.one tendon with.an absorvall lift-off. force .between the predicted lower limit and 905 of the predicted lower limit or with one tendon below 905 of the predicted lomar limit, restore the tendon (s) to the required level of integrity within 15 days and perform an engineering evaluation of the containment and provide a Special Report to the Commission within 30 days in accordance with >
Specification 6.9.2 or be in at least E T STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. .
- b. With any abnormal degradation of the structural integrity other than ACTION a. at a level below the acceptance criteria of Specification 4.6.1.7, restore the containment to the required level of integrity g
within 72 hours and perform an engineering evaluation of the contain-ment and provide a Special Report to the Commission within 15 days in accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. . SURVEILLANCE REQUIREMENTS S R. 3 d. f4 9 4.6.1.7.1 . Containment Tendons. The containment tendons' structural integrity shall be demonstrated at the and of 1, 3. and 5' years following the initial Containment structural integrity' test and at 5 year intervals thereafter. The tendons 0 structural integrity shall be demonstrated by: a." Determining that a randam-but representative spaple of at least 19 tendons (5 done, 6' vertical and 8 hoop) each have an observed lift-off force within predicted limits for each. For each subsequent inspection one tendon from each group any be kept unchanged to develop a history and to correlate the observed data. If the observed lift-off force of any one tendon in the original sample population l lies between the predicted lower limit and 90% of the predicted lower limit, two tendons, one on each side of this tendon should be checked for their lift-off forces. If both.of these adjacent tendons are found to be within their predicted limits, all three tendons should be restored to the required level of integrity. This single deficiency iO may be considered unique and acceeptable. Unless there is abnormal degradation of the containment during the first three inspections, the sample population for subsequent inspections shall include at least 10 tendons (3 dome, 3 vertical, and 4 hoop);
!COMANCHE PEAK - UNIT 1 3/4 6-10A
Socket No. 50-445 CONTAINMENT SYSTEMS Asgust 14, 1987 l OSURVEILLANCEREQUIREMENTS(Continued) 3R 34). 9
- b. Performing tendon detensioning, inspections, and material tests on a previously stressed tendon from each group (dome, vertical, and hoop).
A randomly selected tendon from each group shall be completely detensioned in order to identify broken or damaged wives and deter-mining that over the entire length of the removed wire or strand that:
- 1) The tendon wires or strands are fue of corrosion, cracks, and damage,
- 2) There are not changes in the presence or physical appearance of the sheathing filler-grease, and
- 3) A minimum tensile strength of 1240,000] psi (guaranteed mitimate strength of the tendon material) for at least three wire or strand samples (one from each end and one at mid-length) cut from each removed wire or strand.. Failure of any one of the wire or strand samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.
- c. Performing tendon retensioning of those tendons detensioned for k inspection to their observed lift-off force with a tolerance limit of +6%. During retensioning of these tendons, the changes in load and elongation should be measured simultaneously at a minimum of three approximately equally spaced levels of force between zero and the seating force. If the elongation corresponding to a specific load differs by more than 5% from that recorded during installation, an investigation should be made to ensure that the difference is not related to wire -failures or slip of wires in anchorages;
' d. Assuring the observed lift-off stresses exceed the sveragelrhtinum design value given below, which are adjusted to account for elastic losses; and Dome [143] ksi "
Vertical [147] ksi
.[140] ksi Hoop
- e. Vdifying the OPERABILITY of the sheathing filler grease by:
^
- 1) No voids in excess of 5% of the net duct volume,
- 2) Minimum grease covt. ge exists for the different parts of the anchorage system, and
~
- 3) The chemical properties of the filler material are within the
- tolerance limits as specified by the manufacturer.
[COMANCHEPEAK-UNIT 1 3/4 6-11A
CONTAINMENT SYSTEMS Socket Ilo. 50 445 August 14, 1987 SURVEILLANCE REQUIREMENTS (Continued) SA 3. s. l.1
. 4.6.1.7.2 End Anchorages and Adjacent Concrete Surfaces. The structural integrity of the end anchorages of all tendons inspected pursuant to Specifi-cation 4.6.1.7.1 and the adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage or the concrete crack patterns adjacent
, to the end anchorages. Inspections of the concrete shall be performed during the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment is at its maximum test pressure. . Containment Surfaces. The structural integrity of the exposed
~
- 4. 6.1.7. 3 accessible interior and exterior surfaces of the containment, including the
~
liner plate, shall be determined during the shutdown for each Type A containment leakaDe rate test (reference Specification 4.6.1.2) by a visual inspection of these surfaces. This inspection shall be performed prior to the Type A rentain-ment leakage rate test to verify no apparent changes in appearance or other abnormal degradation. q . e a A
/ COMANCHE PEAK - UNIT 1 3/4 6-12A
CONTAINMENT SYSTEMS So ket No. 50-445 August 14, 1987 CONTAINMENT STRUCTURAL INTEGRITY (Prestressed concrete containment with Os ungrouted tencons ana hemispherical dome.] LIMITING CONDITION FOR OPERATION
- Re h 4 4 . A ida T;;c.L 5 pecs (S ee tJ-k.1i L5.. p A )M i 3.6.1.7 The structural integrity of the containment shall be maintained at a l 1evel consistent with the acceptance criteria in Specification 4.6.1.7. !
I APPLICABILITY: MODES 1, 2, 3, and 4. - 1 1 ACTION: )
- n. With more than onetendon with- en obsened lift-off-force between i the predicted lower limit and 90K of the predicted. lower limit er. I with one tendon below 90% of the predicted lower limit, restore the i tendon (s) to the required level of' integrity within 15 days and ;
perform an engineering evaluation of the containment and provide a Special Report to the Commission within 30 days in accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next i 6 hours and in COLD SHUTDOWN within the followicB 30 hours. .
- b. With any_abnomal degradation of the structural integrity other than ACTION a. at a level below the acceptance criteria of Specification 4.6.1.7, restore the containment to the required level of integrity within 72 hours and perform e.n engineering evaluation of the contain-( l ment and provide a Special Report to the Commission within 15 days in ;
accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVE3tLANCE REQUIREMENTS S 5L 3.L \ .3 .! 4.6.1.7.1 Containment Tendons. The containment tendons' structural integrity shall be demonstrated at the end of 1., 3, and 5 years following the initial ;i containment vessel structural integrity test and at 5 year intervals thereafter. The tendons' structural integrity shall be demonstrated by: '
- a. . Datemining that a random but representative sample of at least 11-tendons (4 inverted U and 7 hoop) each have an" observed lift-off force within predicted limits for each. For each subsequent inspection one tendon from each group may be kept unchanged to develop a history and to correlate the observed data. If the observed lift-off force of any one tendon in the original sample population lies between the predicted lower limit and 90% of the predicted lower limit, two tendons, one on each side of this tendon should be checked for their lift-off forces. If both of thes'e adjacent tendons are found to be within their predicted limits, all three tendons should be restored to the required level of integrity. This single deficiency O- may be considered unique and accceptable. Unless there is abnormal degradation of the containment during the first three inspections, the sample population for subsequent inspections shall include at least 6 tendons (3 inverted U and 3 hoop);
/COMANCHEPEAK-UNIT 1 3/4 6-13A
CONTAINMENT SYSTEMS Sooket 100. 50 445
' - August 14, 1987 SURVEILLANCE REQUIREMENTS (Continued) 3C 3.LlM
- b. Performing tendon detensioning, inspections, and material tests on a previously stressed tendon from each group (inverted U and hoop).
A randomly selected tendon from each group shall be completely detensioned in order to identify broken or damaged wires and deter-mining that over the entire length of the removed wire or strand that: j
- 1) The tendon wires or strands ara free of corrasion, cracks, and damage, j l
- 2) There are not changes -in the presence or physical appearance of f the sheathing filler-gmase, and j l
- 3) A minimum tensile strength of [240,000] psi (guaranteed ultimate strength of the tendon siaterial) for at least three wire or i strand samples (one from each end and one at mid-length) cut from each removed win or strand. Failure of any one of the wire or strand samples to meet the minimum tensile strength -
test is evidence of abnormal degradation af the containment structure.
- c. Performing tendon retensioning of those tendons detensioned for '
b inspection to their observed lift-off force with a tolerance limit of +6%. During retensioning of these tendons, the changes in load and elongation should be measured simultaneously at a minimum of three approximately equally spaced levels of force between zero and the seating force. If the elongation corresponding to a specific load differs by more than 5% from that recorded during installation, an investigation should be made to ensure that the difference is not related to wire failures or slip of wires in anchorages; i
- d. Assuring the obsened lift-off stresses exceed the inverage minimum I design value given below, which are adjustad to account for elastic losses; and Inverted U [139] ksi *.
Hoop: Cylinder (147) ksi a Dome (134) ksi
- e. Verifying the OPERABILITY of the sheathing filler grease by:
- 1) No voids in excess of 5% of the not duct volume,
- 2) Minimum grease coverage exists for the different parts of the anchorage system, and
- 3) The chemical properties of the filler material are within the i tolerance limits as specified by the manufacturer.-
! COMANCHE FEAK - UNIT 1 3/4 6-14A
Socket No. 50-445 CONTAINMENT SYSTEMS August 14, 1987 OSURVEILLANCEREQUIREMENTS(Continued) 4.6.1.7.2 End-Ancheraces and Adjacent Concrete Surfaces. The structural integrity of the end anchorages of all tendons inspected pursuant to Specifi-cation 4.6.1.7.1 and the adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage or the concrete crack patterns adjacent to the end anchorages. Inspections of the concrete shall be performed during the Type A containment leakage rate tests (reference Specification 4.5.1.2) while the containment is at its maximum test pressura. 4.6.1.7.3 Containment surfaces. The structural integrity of the exposed
, accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined during the shutdown for each Type A contain-ment leakage rate test (reference Specification 4.6.1.2) by a visrul inspection of these surfaces. This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparant changes in appearance or other abnormal degradation.
C . i l .,
- e S
O COMANCHE PEAK - UNIT 1 3/4 6-15A
Docket No. 60-445 CONTAINMENT SYSTEMS August I4, 1987 CONTAINMENT STRUCTURAL INTEGRITY [ Reinforced concrete containment)
~
(Ee{ocadcl . ' See /1/s/e /. LIMITING CONDITION FOR OPERATION
- 1 j
3.6.1.7 The structural integrity of the containment shall be maintained at a < level consistent with the acceptance criteria in Specification 4.6.2.7. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: ' With the structural integrity of the containment not conforming to the above ) requirements, restore the structural integrity to within the limits within-24 hours or be in at least HOT STANDBY within the next 5 tiours and in COLD SHUTDOWN : within the following 30 hours. ; 4M SURVEILLANCE REQUIREMENTS l
)
4.6.1.7.1. Containment Surfaces. The structural integrity of the exposed accessible interior anc exterior surfaces of the containment, including the liner plate, shall be determined during the shutdown for each Type A contain-O6 i ment leakage rate test (reference Specification 4.6.1.2) by a visual inspection ; of these surfaces. This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance or other abnormal degradation.
- 4.5.1.7.2 Reports. Any abnormal degradation of the containment structure detected during the above required inspections shall be reported to the Commis-sion in a Special Report pursuant to Specification 6.9.2 within 15 days. 1 This report shall include.a description of the mondith af the manersta, the inspection procedure, the tolerances on cracking, and the 1 corrective actions i{
taken. i i Y y
/COMANCHEPEAK-UNIT 1 3/4 6-16A
l Socket No. 50-445 CONTAINMENT SYSTEMS August.14, 1987 CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION a 3.6.1.8 Each containment purge supply and exhaust isolation valve shall be OPERABLE and: pt.r 1 a.7 ber,u:ricar-cwrganorertr2mIdowthu.% rge, supp c fy and exhaust isola- i Each [42-inch] containment sh ~! tion valve shall be closed and sealed clo ed, and S. MS"ir2h$*~c$Yn" ment #Nroe s# u dlk n xt$st'isolatics valve (s) j may be open for un t.o r10001" hours durine a calendar vaan'>rovided no acre than one pair (one supply and one exhaust) are apen at one time. APPLICABILITY: PODES 1, 2, 3, and 4. 1
# ION sc o 3.% /, conbmc A . .. .L E. !
- a. With a.[42-inch] cent neent purge supply and/or exhaust isolation valve open or not sealed closed, close and seal that valve or isolate the penetration (s) within 4 hours, otherwise be in at least HDT
~ STANDBY within the next 6 hours and in COLD SHUTDOWI within the following 30 hours. De /efed pee LCO 7.5;/;7wdhnk29'a.$ I
- b. With the [B-inch]* containment purge supoly and/or exhaust isolation valve (s)lopen for more than [1030]" hours during a calendar year. F l close the open IB-inch]" valvels) or isolate the penetration (s) within 4 hours, othentise be in at least HOT STANDBY within the next i T 6 hours, and in COLD HUTDOWN within the following 30 hours. l
^ supply and/or exhaust isolation valve (s) !
- c. WikhacoktaYnmYep having a measured leakage rate in excess of the limits of Specifi-cations 4.6.1.8.3 and/or 4.6.1.8.4, restore the inoperable valve (s) to OPERABLE status within 24 hours, otherwise be in at least HOT l STANDBY within the next 6 hours, and in COLD SHUTDOWN within the l following 30 hours. , ,
SURVEILLANCE REQUIREMENTS { l
. 6.L 8.1
[hallbeverifiedtobesealedclosedatleastonceper31 days.Each [42-inch) contahme J, 4.6.1.8.2 The cumulative time that all (4-inch) purge suply and exhaust l isolation valves have been open during a calendar year shall he determined at i least once per 7 days. 1 1
*For a 3-inch valve or less, the valves may be open continuously. For an 8-inch valve or less, the valves may be open for up to 1000 hours during a p calendar year. For an 18-inch valve or less, the valves may be open for up to 500 hours during a calendar year. For a valve greater than 18 inches, the valve say be open for up to 250 hours during a calendar year. All valves that may be open during plant operations (MODE 1, 2, 3, or 4) must be qualified to close under postulated accident conditions. After operational experience, the i licensee may request additional time for the qualified valves to be open T' during plant operations and shall provide justification for the requested additional time as indicated in the Bases.
CDMANCHE PEAK - UNIT 1 3/4 6-17A
CONTAINMENT SYSTEMS Socket No. 50-445 August 14, 1987 . SURVEILLANCE REQUIREMENTS (Continued) S F. 3. r. i. C ( T*:.A Ah'fL T) 4.6.1.8.3 At least once per 184 days on a STAGGERED TEST BASIS, the inboard and outboard isolation valves with resilient material seals in each sealed closed [42-inch) containment purge supply and exhaust penetration shall be demonstrated 0FERABLE by verifying that the measured leakage rate is less than [0.05) L, when pressurized to P ,. 4.6.1.B.4 At least once per 92 days each [8-inch] containment purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than 10.01] L, when pressurized to P, es l e . G I F MANCHE PEAK - UNIT 1 3/4 6-18A
Docket No. 50-445 CONTAINMENT SYSTEMS August 14, 1987 O3/4.6.2 OEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM [ Credit taken for iodine removal) LIMITING CONDITION FOR OPERATION
--- 1.c.c 3.S.3 c.
3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST and transferring suction to the containment sump. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: CcN6tTiON D ANb C.cNb'fTioN E With one Containment Spray System inoperable, restore the inoperable Spray l System to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the inoperable Spray System to DPERABLE status-within the next 48 hours or be in COLD SHUTDOWN within the fallowing 30 tsours. SURVEILLANCE REQUIREMENTS 4 .6.2.1 Each. containment Spray System shall be demonstrated DPERABLE: 5 R 3.5.3.1 At least once per 31 days by verifying that each valve (manual. (O a. power-operated, or automatic) in the flow path that is not . locked, sealed or otherwise secured in position, is in its correct position;
'= s R 3.5. 3
- b. By ver ying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to psig when tested pursuant to Specification 4.0.5;
,_. sn~55.3.4
- c. At least once per 1B months during shutdown, by:
'1) MVerifying that each automatic vartre in the flow path actuates
' to its correct position on a test signal, and
- 2) Verify #ng that each spray pump starts automatically an a test signal.
J 3R 3.5 3.4
- d. At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
O NOMANCHEPEAK-UNIT 1 3/4 6-19A
y I l CONTAINMENT SYSTEMS Docket 50. 50-445
~~ August 34, 1987 1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM [No credit taken for iodine removal) 1 4
LIMITING CONDITION FOR OPERATION _ L t.o 3.5.3 D 3.6.2,1 Twa independent Containment Spray Systems shall be DPERABLE with each 3 Spray System capable of taking suction from the RWST and transferring suction _to the containment sump. : APPLICABILITY: - 9CDES 1, 2, 3 and 4. j { ACTION: ~
. J
-- ccetTitN B mb (ONb'1TiewF - g
- a. With one Containment Spray Systan inoperableand at least (four) 5 containment cooling fans DPERABLE, restore the inaperable Spray System to OPERABLE status within 7 days or be in at least HDT STANDBY within the next 6 hours and in CotD SHUTDOWN within the following 30 hours.
ccchicN D Awd OcM6tticN F .
- b. With two Containment Spray Systems inoperable and at least Ifour) !
containment cooling fans OPERABLE, restore at least one Spray System to OPERABLE status within 72 hours or ce in at' least HOT STANDBY ,Od. within the next 6 hours and in COLD SHUTD0WN within the following 30 hours. Restore both Spray Systems to OPERABLE status within 7 days l of initial loss or.be in at least HOT STANDBY within the next : 6 hours and in COLD SHUTDOWN within the following 30. hours. j c o e 'r6 c N E e n d C c N & tio N F l-
- c. With one Containment Spray System inoperable and one group of j required containment cooling fans inoperable, restore either the j inoperable Spray System or the inoperable group of cooling fans to !
OPERABLE status within 72 hours or be in at least NOT STANDBY within !
- L the next 6 hours and in fala ANUIDOW within the_ followinn 30 hours. l
> Restore both the inoperable Spray System and the inoperable group of- 1 cooling fans to OPERABLE status within 7 days of initial loss or be !
in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN l within the following 30 hours. j 9, l l l i
/ COMANCHE PEAK - UNIT 1 3/4 6-20A
Sooket No. 50-445 CONTAINMENT SYSTEMS SIIRVEILLANCE REQUIREMENTS
~4.62.1 Each Containment spray System shall be demonstrated OPERABLE:
s R 2.5.3.I
- a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position;
- sg 3.5.B.3
- b. By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to psig when tasted pursuant to Specification 4.0.5; I sg 3.5. 3.4
- c. At least once per 18 months, during shutdown, by:
- 1) Verifying that each automatic valve in the flow path actuates to its correct position on a test signal, and
. 2) Verifying that each sprgy pump starts automatically on a test signal.
- - sR 3.5.3.(c
'd. At least once per 5 yects 'q performing an air or smoke flow test through each spray header and verifying each spray noule is unobstructed.
45 ._
'I y
e-
+. I 1
[ COMANCHE FEAK - UNIT 1 3/4 6-21A
l l
)
Docket tio. 50-445 CONTAINMENT SYSTEMS August 14, 1987 i SPRAY ADDITIVE SYSTEM .i I LIMITING. CONDITION FOR OPERATION LCD 3 5.b i T6.2.2 The Spray Additive System shall be OPERABLE with: -l
- a. A spray additive tank containing a volume of between and gallons of between and 3; by weight NaOH 4 solution, and
- b. Two spray additive eductors each capable of adding NaOH solution i from. the chemical additive tank to a Containment . Spray System pump j
.i flow.
l APPLICABILITY: MODES 1, 2, 3, and 4. - CONDIT/OUS A zB ' ACTION: i With the Spray Additive System inoperable, restore the system to DPERABLE status within 72 hours or be in at least HDT STANDBY within the next 6 hours; restore the Spray Additive System to OPERABLE status within the maat 48 hours or be in CDLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS {s l 4.5.2.2 The Spray Additive System shall be demonstrated DPERABLE: SR 3.5.6 I .
- a. At least once per 31 days by verifying that nach valve (aanual, f power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position;
- b. .At.1 mast once per 6 months by: 1
- 1) NMg[i$g 2) the contained edf'y ng the. concentration solution of the"NaOH solution byvoimme chemical in the taji analysis. ]
" I SR 3.5.6 9
- c. At least once per 18 months during shutdown, by verifying that each j automatic valve in the flow path actuates' to its correct position on !
a test signal; and 1 SR 3.6.4.5 d
- d. At least once per 5 years by verifying each solution flow rate (to <
be determined during preoperational tests) from the following drain j connections in the Spray Additive System:
- 1) [ Drain line location) t gps, and v 2) [Drainlinelocation]
- gpm.
s l DMANCHE PEAK - UNIT 1 3/4 6-22A
CONTAINMENT SYSTEMS Socket tio. 50-445 August I4, 1987 , CONTAINMENT COOLING SYSTEM [ Credit taken for iodine removal by spray systems) l iO l LIMITING CONDITION FOR OPERATION
~ Lc.o 3. 5.3 C.- l I
3.6.2.3 [Two] independent groups of containment cooling fans shall be OPERABLE with [two] fan systems to each group. [ Equivalent to 2005 cooling capacity.] ! 5 APPLICABILITY:MODES 1, 2, 3, and 4. ACTIOf4 - CoNomoN A ngd. OcNbmOM G l a. With one group of the above required containment cooling fans inoper- ! , able and both Containment Sprey Systems OPERABLE,~ restore the inoper- 1 able group of cooling fans to DPERABLE status within 7 days or be in at least HDT STANDBY within the next 6 hours and in CDLD SHUTDOWN . I within the following 30 hours. ) CDNDiTtDN B SMcl OcNbiTICM G
- b. With two groups of the above required 1 containment cooling fans inoperable and both Containment Spray Systems OPERABLE, restore at least one group of cooling fans to CPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restere both above required
, groups of cooling fans to OPERABLE status within 7 days of initial 3 l loss or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. ,k. cDNbnicy c AND CONDITION G l c. With one group of the above required containment cooling fans inoper-able and one Containment Spray System inoperable, restore the inoper-able Spray System to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN
~
within the following 30 hours. Restore the inoperable group of containment cooling fans to OPERABLE status within 7 days of initial loss or be in at least HDT STANDBY within the next 6 hours and in l . COLD SWIDOWN within the following 20 hours. 1 i SURVEILLANCE REQUIREMENTS . 4.6.2.3 fach g of containment cooling fans shall be demonstrated DPERABLE: )
- a. Ibeast once per 31 days by: ,
- 1) Starting each fan group from the control room, and verifying !
that each fan group operates for at least 15 minutes, and
- 2) Verifying a cooling water flow rate of greater than or equal to
_ gpm to each cooler. sR 3.5.3.C
- b. At least once per 18 months by verifying that each fan group starts h' _
automatically on a test signal.
/COMANCHEPEAK-UNIT 1 3/4 6-23A
. 45 CONTAINMENT SYSTEMS O CONTAINMENT COOLING SYSTEM [No credit taken for iodine removal LIMITING CONDITION FOR OPERATION
"-- LC.O 3 5.3 D 3.6.2.3 [Two) independent groups of containment cooling fans shall be OPERABLE with [two) fan systems to each group. [ Equivalent to 100% cooling capacity.)
~
4 APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: COND'ITiON fh AND OcNDIT5DME
- a. With one group of the above required containment tooling fans inoper-
~able and both Containment.5 pray Systems OPERABLE. restore the inoper-able group of cooling fans to DPERABLE status within 7: days or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within ,the following 30 hours. j O conDmcN C Mb CDMbmoN1F With two groups of the above required containment tooling fans-
- b. I' inoperable and both Containment Spray Systems OPERABLE, vestore at least one group of cooling fans to OPERABLE status within 72 hours or be in at least HOT STANDBY e4 thin the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restore both above required groups of cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours and in fO COLD SHUTDOWN within the following 30 hours.
;C Cot crnbiTicN F
- c. With@m0N E MI) one group of the'above required containment tooling fans inoper-able and one Containment ~ Spray System inoperable, restore either the inoperable group of containment cooling fans or the inoperable Spray System to OPERABLE status within 72 hours or be in at least HDT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restore both the inoperable group of contain-ment cooling fans and the inoperable Spray System to OPERABLE status
.,within 7 days of initial loss or be in at least HDT STANDBY within
' the next 6 hours land in 4.1RLB SMUTDOWN witsein the fa11owing 30 hours.
SURVEILLANCE REQUIREMENTS 1 4.6.2.3 E of containment cooling fansishall be demonstrated OPERABLE:
. 2_
east once per 31 days by: a.
- 1) Starting each fan group from the control room and verifying j
that each fan group operates for at least 15 minutes, and '
- 2) Verifying a cooling water flow rate of greater than or equal to a to each cooler.
- b. t ea once per 18 months by verifying that each fan group starts automatically on a test signal.
i s
/CDMANCHEPEAK-UNIT 1 3/4 6-24A
I 45 CONTAINMENT SYSTEMS SDC N 3/4.6.3 IODINE CLEANUP SYSTEM
- I l
LIMITING CONDITION FOR OPERATION I.
>i
) co 3.5./t ;
T.6.3' Two independent Iodine Cleanup Systems shall be OPERABLE. I APPLICABILITY: MODES 1, 2, 3, and 4. gcnoris A ntC. With cne lodine Cleanup System inoperable, restore the inoperable system to " 1 OPERABLE status within.7 days or be'in at least HOT STANDBY within the anxt 5 hours and in COLD SHUTDOWN within the following 30 hours.
. j 1
SURVEILLANCE REQUIREMENTS 4.6.3 Each Iodine Cleanup System shall be demonstrated DpIRABLE: ~ 5 g 3.5. /E /
- a. At least once per 31 days 'on a STAGGERED TEST BASIS try initiating, from the control room,. flow through the HEPA filters and charcoal
< , adsorbers and' verifying that the system operates for at least
- 10 continuous hours with the heaters operating; Spic o f*ED tvo ra A Ph.* cot 4t i~ Sun /5*u *4kL*3
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical- release in any ventilation zone communi-cating with the system by:
SR 3. 5. /4'.2 RND S R., 3.5 '1 3 l
- 1) Verifying that the cleanup system satisfies the in place penetra-
, ,j "- tion and typass. leakage testing acceptance criteria of less than [
- . I*]% and uses the test procedures guidance in Regulatory Positions
.C.5.a, C.5.c, and C.S.d of Regulatory Guide 1.52. Revision 2. -
'Merch 1978, and the systas flow rata is efs 1 10%.
s R 3.r./+'.4 q 2)c Verifying within 31 days after removal, that a laboratory analy- l sis of a representative carbon sample obthined in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revi-
'sion 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2,
- March 1978, for a methyl iodide penetration of less than [**3%; ;
and s R 3. S. M.5
- 3) Verify %n a system flow rate of 'cfm i 10% during system operation when tested in accordance with ANSI N510-1975.
1
/ /COMANCHEPEAK-UNIT 1 3/4 6-25A
l l i Docket 50. 50-445 , CONTAINMENT SYSTEMS August 14, 1987 l l i D SURVE1LLANCE REQUIREMENTS (Continued)
\
I S R 3. 5./'t. f
- c. After every 720 hours of charcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a repre- !
sentative carbon sample obtained in accordance with Regulatory Posi- ! tion C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, meets- l the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a mettlyl iodide l penetration of less than [**]%; .
- d. At.least once per 18 months by:
S K 3. 5./4.5 1
- 1) Verifying that the pressure tirop across the combined HEPA j filters and charcoal adsorber banks is less than [6] inches d Water Gauge while operating the system at a flow rata of cfm i 10%;
5 4 3.5./+.6
- 2) Verifying that the system starts on either a Safety Injection test signal or on a Containment Pressure-High test signal; .
S K 3.S.lf.7
- 3) Verifying that the filter cooling bypass valves can be apened by. operator action; and ,
S R 3.5./Y.B ,
- 4) Verifying that tne heaters dissipate t kW when tested in accordance with ANSI 1510-1975. l 5 /C 3.6./t.2.
~
- e. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place penetration and by leakage testing acceptance criteria of less than [*]% in accordance with ANSI H510-1975 for a DOP test aerosol while operating .
the system at a flow rate of cfm t 10%; and j S L 2. 5. H.3 )
- f. After each complete trr partial uplacement of a tharcoal adsorber ,
bank, by verifying that the cleanup system satisfies the in-place l l
~
penetration and bypass leakage testing acceptance criteria of less than [*]% in accordance'with ANSI M510-1975 for a halogenated , hydrocarbon refrigerant tast, gas while operating the, system at a 1 _,,,f low rate of cfm i 10%. - 19PPLicnet.c veufs Mctuoso te nestsa.t.nacs/owssrou ty gesn
*0.05% value applicable when a HEPA filter er charcoal adsorber efficiency of 99% is assumed, or 1% when a HEPA filter or charcoal adsorber efficiency of 95% or less is assumed in the NRC staff's safety evaluation. (Use the value assumed for the charcoal adsorber efficiency if the value for the HEPA filter is different from the charcoal adsorber efficiency in the NRC staff's safety evaluation).
**Value applicable will be determined by the following equation:
P=I S , when P equals the value to be used in the test requirement-
- (%), E is efficiency assumed in the SER for methyl iodide removal (%),
and SF is the safety factor to account for charcoal degradation between tests (5 for systems with heaters and 7 for systems without heaters). 1 A
/ COMANCHE PEAK - UNIT 1 3/4 6-26A
CONTAINMENT SYSTEMS < Docket No. 50-445
' August 14, 1987 3/4.6.4 CONTAINMENT ISOLATION VALVES l LIMITING CONDITION FOR OPERATION 2>s /e fe d ber- L c0 2 5" / ns 6 *Ce'.4c's ::tVs , .i .
3.6.4 The containment isolation valves specified in Table 3.6-1 shall be j
-1 OPERABLE with isolation times as shown in Table 3.6-1.
APPLICABILITY: M)DE5 1, 2, 3, and 4. , ACTION:
- Leo 3.5;j cc Amesr5 ,k enal E; i
*With one or more.cf the isolstion valve (s).specified in Table 3.5-11noperable, maintain at least one isolation valva DPERABE in each affected penetration.
that is open.and. , q
- a. Restore the ir. operable valve (s) to DPERABE status within 41:aurs, or
- b. Isolate each affected penetration Mthin 4 hours by use of at least one deactivated automatic valve secured in the isolation position, or .
- c. Isolate each affected penetration within 4 hours by use of et least 4 one closed manual valve or blind flange, or
't .
- d. Be in at least NOT STANDBY within the next 5 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS
' l 3ekN per- 4 c-o 3. 5" / J~an % %e 1%m F. )
4.6.4.1 "The isolation valves specified in Table 3.5-1 shall be demonstrated ; DPERABLE prior 4o returning the valve to service after maintenance, repair or ! replacement work is performed on the valve or its associated actuator, control , or power circuit by performance of a cycling test, and verification.of isola- l tion time. i beh& )3Le- $~ C O E * $~ l N / 0% 9.
- CAUTION: The inoperable isolation valve (s) may be part of a system (s).
-( Isolating the affected penetration (s) may affect the use of the systee(s).
/ Consider the technical specification requirements on the affected system (s) and act accordingly.
/ COMANCHE PEAK - UNIT 1 3/4 6-27A
1 Sscket No. 50-445 l CONTAINMENT SYSTEMS Asagust 14, 1987 i SURVEILLANCE REQUIREMENTS (Continued) 4.6.4.2 Each isolation' valve specified in Table 3.5-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
.. : R 3 . 5. /. 4
- a. Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position; l
54 3.E /.9 T Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position; and l 54 3. r; /.T
- c. Verifying that on a Containment Purge and Exhaust Isolation . test signal, each purge and exhaust valve actuates to its isolation ,
l position.
~
.S_R3.r.i.z 4.6.4.3 The isolation time of each power-opented or automatic ^ valve of Table 3.6-1 shall be determined to be within its limit when tasted pursuant to Specification 4.0.5. .
U .
~
e j u I
'a' e
j DMANCHE PEAK - UNIT 1 3/4 6-28A
O l s d n o c e S ( M . UE l _ MM o II XT r l A h MN o . O
- t I
_ S T e - E A v V L i . L O t e A S a l V I_ r b t a N s c 1 O i i
- I n l T i p
. A m p L . d a Q a S t L
B I r o A T e n T N d E n e M u r M a I s A i 4 T s N N as0 O D bt C 1 s3 T te C t nt n N s e o U u ' t ei t gt F a iaa h x mk rai c E eef d tIi n n .c
,n n a ice o o p i i e neS t t g i
- ap a a r yf l l u nTo o
o o P s s os I t dt n I n e o e nti "A "B m ecs pei R " " n ojv E l l B e e a a r bo M s s t u e eur U a a n n h bsp N h * . . h . . o - . a . . t . . P
- b P a b C *6 M a b O a b yt e aoh E
V MMT L A . . . . . * *
)Q' V 1 2 3 4 5
- 7-
,gh'AR.EZw
" Ylg"
i I I Socket No. 50 445 l CONTAINMENT SYSTEMS August 14, 1987 l q 3/4.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS LIMITING CONDITION FOR OPERATION
' LCC ?,5 m j 3.6.5.1 Two independent containment hydrogen monitors shall be DPERABLE. l APPLICABILITY: HDDES I and 2.
ACTION: 4, . .x c. , 2a.:-o With 3.: iQ, one .cc,xfriuItor hydrogen mon inoperable, restore the inoperable monitor to 1 OPERABLE status within 30 days or be in at least HDT STANDBY within the 1 next 6 hours. l LC 0 3.f: /)> cc,at,, -7, c,9 $ 'p, e J C.
- 1
- b. With both hydrogen monitots inoperable. Testore at least vne sonitor to i
DPERABLE status within 72 hours or be in at least HDT STANDBY within the next 6 hours. I i [ SURVEILLANCE REQUIREMENTS
^
Y V SR 3. r.19. t , sn 3.ri9. 2. , 64 re s. s: m,3 \ 4.5.5.1 Each hydrogen monitor shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK at least once per 12 hours, an ANALOG CHANNEL OPERATIONAL : TEST at least once per 31 days, and at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gas containing: l
- a. One volume percent hydrogen, balance nitrogen, and ..
I
- b. 'Four volume percent hyJ,.,co, balance mL-pu.
H
\
1
)
l OMANCHE PEAK - UNIT 1 3/4 6-30A
Socket No. 50-445 CONTAINMENT SYSTEMS , August.14, 1987 - ELECTRIC HYDROGEN RECOMBINERS LIMITING CONDITION FOR OPERATION L cc 3, !~ itr 4 (an,c s c 0 3.c~ Ig8} . 3.6.5.2 Two independent Hydrogen Recombiner Systems'shall be DPERABLE. APPLICABILITY: MODES ,1 and 2. ACTION: C". C/JL)t=r s c fj~g f, a n d C, , With one Myorogen NeConD1ner System inoperable, restore the inoperable system . to OPERABLE status within-30 days or be in at least HDT STANDBt' within the' ' next 6 hours. SURVEILLANCE REQUIREMENTS 4.6.5.2 Each Hydrogen Recombiner System shall be demonstrated OPERABLE: - SR 3. f./ T. / -
- a. At least.once per 6 months by verifying, during a Hydrogen Recombiner System functional test, that the minimum heater sheath temperature increases to greater than or equal to [700]'F within (90] minutes.
( Upon reaching [7003'F, increase the power setting to maximum power for 2 minutes and verify that the power meter reads greater than or. equal to [60] kW, and
- b. At least once per "18 months by:
- 43. 3. C 17 2. *
- 1) Performing a CHANNEL CALIBRATION of all recmubiner instruments-tion 'and control circuits, ]i 54 3:5 /F.3
- 2) . Verifying through a visual examination that them is no
~ '
- a. evidence of abnormal conditions within the vernehiner enclosure (i.e., loose wiring or structural connections, deposits of A s foreign materiais,-etc.), and q T43.n q.y . ;
- 3) Verifying the integrity of all heater ele,ctrical circuits by ;
performing a resistance to ground test following the above i I required functional test. The resistance to ground for any ; heater phase shall be greater than or equal to 10,000 ohns. ; 0MANCHE PEAK - UNIT 1 3/4 6-31A
k 0 0 t eT he.cs het N0fe_ $) Socket No. 50-445 CONTAINMENT SYSTEMS August.14, 1987 HYDROGEN PURGE CLEANUP SYSTEM [If less than 2 hydrogen recombiners available] I LIMITING CONDITION FOR OPERATION 3.6.5.3 A Hydrogen Purge Cleanup System shall be DPERABLE and capable of being powered from a minimum of one OPERABLE emergency bus. APPLICABILITY: MODES 1 and 2. ACTION: With the Hydrogen Purge Cleanup System inoperable, wstore the R,7J won Purge Cleanup System to DPERABLE status within 30 days or be in at least HDT STANDBY within 6 hours. SURVEILLANCE REQUIREMENTS 4.6.5.3 The Hydrogen Purge Cleanup System shall be demonstrated DPERABLE:
- a. At least once per 31 days by initiating, from the control room, flow 4 through the HEPA filters and charcoal adsorbers and verifying that I the system operates for at least 10 continuous hours with the heaters operating;
- b. At least once per IB y,onths or (1) after any structural maintenance of the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:
f
~1) . Verifying that the cleanup system satisfies the in place penetre-tion and bypass leakage testing acceptance criteria of less than
[*]% and uses the test procedure guidance in Regulatory Posi - tions C.S.a. C.S.c. and C.5.d of Regulatory Guide 1.52, Revision 2 March 1978, and the system-flow fate is- . cfm i 10E; I) Verifying, within 31 days after removal,"that a laboratory analy-sis of a representative carbon sample obtained in accordance
~
l I with Regulatory Position C.6.b of Regulatory Guide 1.52, Revi-l : sion 2, March 1978, meets the laboratory testing criteria of . v Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than [**3%: l and l
- 3) Verifying a system flow rate of cfm i 10% during system l
. operation when tested in accordance with ANSI N510-1975. l b
l f L.CDMANCHE' PEAK - UNIT 1 3/4 6-32A
i% *44l [ % 4kfe f } CONTAINMENT SYSTEMS Booket tio. 50-445 August 14, 1987 l SURVEILLANCE REQUIREMENTS (Continued) i
- c. After every 720 hours of chercoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtaint4 in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March .1978 for a methyl fodide penetration of less than 1**.3%;
. d. At least once perJS sonths by:
l 1) Verifying that the pressure drop across the codbined HEPA
' filters and charcoal adsorber banks is less than [6] inches Water Gauge while operating the system at a flow rate of cfa 2 10%,
- 2) Verifying that the filter cooling bypass valvas man .be manually opened, and _
i
- 3) Verifying that the heaters dissipate
- Mf when I tested in accordance with ANSI N510-E
- e. After each complete or partial replacement of a HEPA filter tank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than [*]% in accordance with ANSI N510-1975 for a DOP test aerosol while operating the system at a flow rate of cfm *.10%; and ,
- f. After nach complete or partial replacement of a charcoal adsorber bank, by ver*fying that the cleanup system satisfies the in place ;
penetration and bypass leakage testing acceptance criteria of less than I*]% in accordance with ANSI M510-1575 for a halogensted
- hydrocarbon refrigerant test gas while operating the system at a flow rate of cfm i 10%.
*0.05% value applicable when a HEPA filter or charcoal *adsorber efficiency of 99% is assumed, or 1% when a HEPA filter or charcoal adsorber efficiency of l 95% or less is assumed in the NRC staff's safety avaluation. (Use the value :
assumed for the charcoal adsorber efficiency if the value for the HEPA filter i is different from the charcoal adsorber efficiency in the NRC staff's safety ! evaluation.) l
**Value applicable will be determined by the following equation:
P=1 -E , when P equals the value to be used in the test requirement O (%), E is efficiency assumed in the SER for methyl iodide removal (%), and SF is the safety factor to account for charcoal degradation between tests (5 for systems with heaters and 7 for systems without heaters).
. COMANCHE PEAK - UNIT 1 3/4 6-33A
__ --_ -- L
i Socket No. 50-445 CONTAINMENT SYSTEMS Ansgust 14, 1987 l Q(j HYOROGEN MIXING SYSTEM LIMITING CONDITION FOR OPERATION I u -c ?. n /9 3.6.5.4 Two independent Hydrogen Mixing Systems shall be DPERABLE. APPLICABILITY: MODES 1 and 2. ACTION: A CC 3 . .G i 9 CcNO/T'tDNS 4. an (_ C. : With one Hydrogeh Mixing System inoperable, restore the inoperable system to DPERABLE status within 30 days:or be in at- least WT STAND 8Y within the next' ] 6 hours. j SURVEILLANCE REQUIREMENTS 4.6.5.4 Each Nydrogen Mixing System shall be demonstrated DPERABLE: 1 FR 3,5~./t./ l
- a. At least once per 92 days on a STA'iGERED TEST BASIS by starting each I e
system from the control room and verifying that the system operates l e for at least 15 minutes, and l i M 3. C /P.3 D. At least once per 18 months by verifying a system flow rate of at least efs. I 1 a
'l
-r
~ '
N kDMANCHEPEAK-UNIT 1 3/4 6-34A
Socket No. 50-445 CONTAINMENT SYSTEMS Ansgust 14, 1987 O3/4.6.6 PENETRATION ROOM EXHAUST AIR CLEANUP SYSTEM LIMITING CONDITION FOR OPERATION LC0 3.6.15 1.6.6 Two independent Penetration Room Exhaust Air Cleanup Systems shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. 3CTION: With one Penetration Room Exhaust Air. Cleanup System inoperable, wstom the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours and in IDLD SHUTDOWN within the following
}_0 hours.
SURVEILLANCE REQUIREMENTS 4.6.6 Each Penetration Room Exhaust Air Cleanup System shall be demonstrated DPERABLE: s R 3.5. / 5. / . !'
- a. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least IC continuous hours with the heaters operating; S PEctFtED W sTri RPP2 s cA 612 :5WtH u nWC'S
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi- 1 cating with the systam by: 3
' SR S.5.t 6.2. 4 S R 3.5 'F 3 1
- 1) Verifying that the cleanup system satisfies the in place pene-tration and bypass leakage testing acceptance criteria of less :
- than [*]% and ases the test procedure guidance in Regulatory 1 Positions C.S.a. C.5.c, and C.S.d.of Regulatory Guide 1.52, i Revision 2, March 1978, and the system f1'ow rate is cfm i
- 10%; j SR 35./54 j 4
; 2) Verifying, within 31 days after removal, that a laboratory analy-sis of a representative carbon sample obtained in accordance with < - Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, ,
March 1978, meets the laboratory testing criteria of Regulatory Position C.S.a of Regulatory Guide 1.52 Revision 2, March 10?*, for a methyl iodide penetration of less than [**3%; and t
!COMANCHEPEAK-UNIT 1 3/4 6-35A
4 CONTAINMENT SYSTEMS gooket No. 50 445 August 14, 1987 SURVEILLANCE REQUIREMENT 5 (Continued) j S R 3.5./5. 5
- 3) Verifying a system flow rate of cfm 1 10% during system operation when tested in accordance with ANSI N510-1975.
c. S R 3. 5.15. 4 After every 720 hours of charcoal adsorber operation, by verifying. within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2. March 1978, j meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2. Marchl97A. for a methyl iodide penetration of less than f**JE;
- d. nths by:
Atleastencygr
- 3) Veriffingthatt pressureifrop across the combined HEPA 4
. filters and charcoal adsorber banks is less than I6] inches Water Gauge while sperating the system at a flow rate of
* * # Yb.5.15.6
- 2) Veriffing that the systes starts an a Safat,y Jtdection test signal
- 3) Verif gt t'he filter cooling bypass valves can be manually opened and
. S . /5. 8
- 4) Veri ng hat the heaters dissipate t kW when tested in accordance with ANSI N510-197F - .
SR ' 3.5.15.2 e. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system sai.isfies the in place penetra- j tion and bypass leakage testing acceptance criteria of less than [*]E .i in accordance with ANSI M510-1975 ing the system at I flow rate of for a DOP cfm t test 3DK,aerosoland while operat-S R 3. 5.15. 3 ;
- f. i After each complete or partial replacement of a charcoal adsorber !
bank, by verifyfog that the cleanup system' satisfies the in place ) penetration and bypass leakage- testing acceptance criteria of less j
. than [*)% in accordance with ANSI N510-1975 for a halogenated j hydrocarbon refrigerant test 9as while operating the system at a flow rate of cfm i 10%. .
i
~
APPucABL E YttwcS MCta0ED IM 5M.bl&a56MCES/WM M 50.05% value applicable when a HEPA filter er charcoal adsorber efficiency of 99% is assumed, or 1% when a MEPA filter or charcoal adsorber efficiency : of 95% or less is assumed in the NRC staff's safety evaluation. (Use the ! value assumed for the charcoal adsorber efficiency if the value for the HEPA filter is different from the charcoal adsorber efficiency in the NRC staff's safety evaluation.)
**Voke applicable will be determined by the following equation:
P = 10p3-E
, when P equals the value to be used in the test requirement O.
(%), E is efficiency assumed in the SER for methyl iodide removal (%), and SF is the safety factor to account for charcoal degradation between tests (5 for systems with heaters and 7 for systems without heaters).
/ COMANCHE PEAK - UNIT 1 3/4 6-36A
- l
l I Docket No. 50-445 CONTAINMENT SYSTEMS August 14, 1987 e - y 3/4 6.7 VACUUM RELIEF VALVES l LIMITING CONDITION FOR OPERATION 4c- c 3. 0 9
- l. 3.6.7 The primary containment to atmosphere vacuum relief valves shall be OPERABLE with an Actuation Setpoint of less than or equal to psid.
APPLICABILITY: K) DES 1, 2, 3, and 4. { ACTION: L C-C 3. C 9 c t sjbiri sns 4. e nel c. With..one- prisiary containment to atmosphere vacuum' relief valve bwele, {' restore the valve to OPERABLE status within 4 hours or be in at least HOT STANDBY within the next 6 hours and in C0j.D SHUTDOWN within the' following 30 , hours.
)
i v.. SURVEILLANCE REQUIREMENTS I E R 3. T. '?. / 4.6.7 No additional requirements other than those required by Specifica-tion 4.0.5. i j l
-l
}
.. l 1
1 1 u f e. 0MANCHE PEAK - UNIT 1 3/4 6-37A
Socket Ilo. 50-445 ,
- August.I4, 1987
>\ l i
i J a i 1 l 1 J SECTION 3[4 lib CONTAINMENT SYSTDt5 SPECIFICATIONS 1 FOR
' WESTINGHOUSE ICE CDNDENSER TYPE CONTAINMENT y,
i
; sq s
- COMANCHE PEAK - UNIT 1 3/4 6-08
-Docket No. 50-445 August 14, 1987 9; 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT -
~
CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION l CO 3. E / 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained. APPLICABILITY: . MODES 1, 2, 3, and 4. ACTION: ~
,,.S C A/0/7/o A/y 3. *
- c/ E.
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENTINTEGRITf within 1 hour or be in at least NOT STANDBY within the next 6 hours and in .CDJ.D
- SHUTDOWN within tne following 30 hours.
SURVEILLANCE REQUIREMENTS 94.6.1.1
\
Primary CONTAINMENT INTEGRITY shall be demonstrated: TR 3. F.I. /
- a. At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, o~r deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.4; "
S R 3 . T /. 4 a--L 3R 3. .C /.f* LSee Alck 1.) T 'By verifying that each containment air lackis fa zampliance with d
~the requirements of Specification 3.6.1.3; and
- S'R 3.
- c. T. /.'5-After each(see Ucie closing 7) ch penetration subject to Type B testing, of..ea except the containment air locks, if opened following a Type A or E l test, by leak rate testing the seal with gas' at a pressure not less ;
than P,, [20 psig), .and verifying that when the sensured leakage rate ; for these seals is added to the leakage rates determined pursutnt to
$ specification 4.6.1.2d. for all other Type S and C penetrations, the 1 combined leakage rate 'Is less than 0.60 L,.
SR 37 /. 2 l l
*Except v b es, b1tod flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured 9 '
in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days. i COMANCHE PEAK - UNIT 1 , 3/4 6-1B
Socket Mo. 50-445 August-14,1987 9CONTAINMENTSYSTEMS CONTAINMENT LEAKAGE v/; .3. f~. /. T~ (see Nt1e 7,) LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of:
- 1) Less t.han er equal to L,, [0.203 % by assicht of the containmerit air per 24 hours at P,, [20 psig], or
- 2) Less than er equal to it. [0.14] E by eseight af the soittaiment air per 24 hours at a reduced pressure of g P , W W.
- b. A combined leakage rate of less than D.6D L, for all penetrations and valves subject to Type S and C tests, when pressurized to P,,
and
- c. A combined bypass leakage rate of less than or equal to [D.1D3 L, for all penetrations identified in Table 3.6-1 as secondary contain-ment bypass leakage paths when pressurized to P,.
APPLICABILITY: MODE 5 1, 2. 3, and 4. ACTION: With: (a) the measured overall integrated containment leakage rate exceeding D.75 L , or D.75 Lg . as applicable, or (b) the measured combined leakage rate for all 1 penetrations and valves subject to Types B and C tests exceeding 0.60 L,,'er (c) the combined bypass leakage rata exceeding [0.1D] L ,, restore the overall integrated leakage rate to less than 0.75 L, or :less than'O.75 gi , as applicable, j i and the combined leakage rate for all penetrations and valves' subject to Type B and C tests to less than D.60 L,, and the combined bypass leakage rate to less f than [0.10) L, prior to increasing the Aeactor Coolant System temperature above 1
'200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following , test schedule and shall be Ntermined in conformance with the criteria speci- i l fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-[1972): CDMANCHE PEAK - UNIT 1 3/4 6-2B i
o 1 Socket No. 50-445 August-14, 1987 y CONTA]NMENT SYSTEM 5 , S.t3,S/.3-CcoeTv4.1) SURVE1LLANCE REQUIREMENTS (Continued)
- a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40110 month intervals during shutdown at either P,, [20 psig], or at P g, [10 psig], during each 10 year ser- l vice period. The third test of each set shall be conducted during -l a
the shutdown for the 10 year plant inservice inspection;
- b. If any periodic Type A test fails to meet either 0.75 L, or D.75 Lg ,
the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Ty A tests fai1~to . seet either D.75 L, or 0.75 L g,-a Type A test shai, he performed at least every 18 months amtil two consecutive Type 4 tests east either 0.75 L, or 0.75 Lt at which time the above test schedule any.te resumed; q
- c. The accuracy of each Type A test shall be verified by a supplemental )
test which:
- 1) Confirms the accuracy of the test by verifying that the supple-mental test rescit, i ,gis in accordance with the appropriate following equation:
l L, - (L,, + L,_) 1 $ 0.25 L, or l L, - (L g, + L,) 1 $ D.25 L, where L,,or Ltm is the measured Type A test laakage and L, is the superimposed leak;
- 2) Has a duration sufficient to establish accurately the thange in leakage rate between the Type A test and the supplemental test; and
- 3) Requires that the rata at which gas is injected into the contaire j
- ment or tied from the containment during the supplemental .tast
.is between 0.75.1, and 1.25 L,; or 0.75Lgand 1.25 L g._
~d. Type 8.and C tests shall be conducted with gas at a pressure not less i than P,, [20 psig], at intervals no greater than 24 months except for j
tests involving: )
- 1) Air-locks,
- 2) Purge supply and exhaust isolation valves with resilient material !
i seals,
- 3) Penetrations using continuous Leakage Monitoring Systems, and
- 4) Valves pressurized with fluid from a Seal System.
- e. The combined bypass leakage rate shall be determined to be less than
( or equal to [0.10] L, by applicable Type B and C tests at least once per 24 months except for penetrations which are not individually test-able; penetrations not individually testable shall be determined to j COMANCHE PEAK - UNIT 1 3/4 6-3B
Docket No. 50-445 August 14, 1987 ( CONTAINMENT SYSTEMS l g( l
. SURVEILLANCE REQUIREMENTS (Continued)
E& 3.r. t.r(c ~~&w MJ have no detectable leakage when tested with soap bubbles while the ( containment is pressurized to P,, [20 psig], or P g . [10 psig], Mng l l each Type A test;
- f. Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements af Specification 4.6.1.10.3 or 4.6.1.10. 4, as applicable. ;
i
- g. Air locks shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.3;
- h. Type B periodic tests are'not required for penetrations continuously monitored by the Containment Isolation Valve and Channel tield Pres-surization Systems, provided the systems are OPERAR15 by the require- ,
ments of Spec 1fication 4.6.1.4; l i l
- 1. Leakage from isolation valves that are sealed with fluid from a Seal System may be excluded, subject to the provisions of Appendix J, Section III.C.3, when determining the combined leakage-rate mvided
[22 U theSealSystemandvalvesarepressurizedtoatleast1.10P}s, psig], and the Seal System capacity is adequate to maintain s tem ! prescure for at least 30 days; l 1
- j. Type B tests for penetrations employing a continuous Leakage Monitor-ing System shall be conducted at P,120 psig], at intervals no greater '
than once per 3 years; and
- k. The provisions of Specification 4.D.2 are not applicable. ]
i
'i i
i COMANCHE PEAK - UNIT 1 3/4 6-4B
'Becket No. 50-445 August 14, 1987
- n. , n=, , s, . a,
\
. a 5
2 '5 a S
? u 4 a
^
2 2
- E a f 9 W 2
3 a E 2 E B k i 8 .- 1 - i 1 9 1 2 0
=
I COMANCHE PEAK - UNIT 2 3/4 6-5B I
-_ _ i
Socket tio. 50-445 August- 14, 1987 CONTAINMENT SYSTEMS
'k CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be DPERABLE with:
** i MP/J.UTIL N5 - CoAIT4/A4*J" EN 'T :fN 4 l'# y W N m N.
- a. Both doors closed except when the air k is hing used for normal transit entry and exits through the containment, then et least one air lock door shall be closed. and SR M we ) [1eakage rate af less than -or squal D D.05 L,
'T. .3.An 5~over h r $14 atr' toc at P,, [20 psig]. ,
APPLICABILITY: 9tDDES 1, 2, 3, and.4. . - ACTION: 1 L c c 3. i~. I C D.)LITiG/JS .B. e n=l E. '
- a. With one containment air lock door inoperable:
- 2. Maintain at least the DPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within i 24 hours or lock the DPIRABLE air lock door closed.
' k l
- 2. Operation may then continue until perfomance of the next l required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at laast once per 31 days, -
l- ~ 3. Othetvise, be in at least NOT STANDBY erithin the next 6 hours and in COLD SHUTDOWN within the following 30 hours, and { j
.4.1The provisions of Specifiestion 3.D.4"are not-applicable. i J. C. 0 95/ CONO!'TiGNs c.no.! E.
. D. With the containment air lock inoperable, except as the result of an ,)
inoperable air ~10ck door,:astatain at least one air lock door closed; ,~ restore the inoperable air lock to.0PEBABLE status within 24 hours or be in at least NOT STANDBY within the.next 5 hours and ia COLD l SHUTDOWN within the following 30 hours. i 1 (s COMANCHE PEAK - UNIT 1 3/4 6-6B --
Becket No. 50-445 August 14, 1987 Q
) CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
SR
- a. 3.WithinF. /.r72 (5ee Alo-fe hours g) each closing, except when the air lock is following being used for multiple entries, then at least once per 72 hours, by verifying that the seal leakage is less than 0.01 L, as determined by precision flow measurements when measured for at least 30 seconds
- with the volume between the seals at 4 sonstant pressure of 12D psig];
- t. Sy renducting overall eir lect leakage tests at not less than P,,
[2D psig), and verifying the everall air lock ~1eakage 1nate is within its limit:
- 1) At least once per 6 months.* and
- 2) Prior to establishing CONTAINMENT INTEGRITY when inaintenance has been performed on the air lock that could affect the air lock sealing capability.**
5 R 3.AtCleast/. a once per 6 months by verifying that only one door in each T , air lock can be opened at a time. I l l 4 b SR 3. 5' J.T (See Alote 7)
*The provisions of Specification 4.0.2 are not. app % cable, j
**This represents an exemption to Appendix J, paragraph III.D.2.(bXii), of i
l 10 CFR Part 50. [ Applicant must request this aneuption.] Li i i f
't.
C0MANCHE PEAK - UNIT 1 3/4 6-78
i Socket No. 50-445 . CONTAINMENT SYSTEMS N./ CONTAINMENT ISOLATION VALVE AND CHANNEL WELO PRESSURIZATION SYSTEMS S R 3. r. l.f (Tse A*ft- ?) LIMITING CONDITION FOR OPERATION ] 3.6.1.4 The Containment Isolation Valve and Channel Wald Pressurization Systems shall be OPERABLE. i APPLICABILITY: MODES .1, 2, 3, and 4. t ACTION: } l With the Containment isolation Valve or Channel W1d Pressurization System inoperatie, restore the inoperable system to OPERABLE status within 7 days 1er j be in at least HDT STANDBY within the next 6 hours and in EOLD SMITDDWN within the following 30 hours.
/ SURVEILLANCE REQUIREMENTS
(, 4.6.1.4.1 The Containment Isolation Valve Pressurization System shall be demonstrated OPERABLE at least once per 31 days by verifying that the system ; is pressurized to greater then or equal to 1.10 P,, [22 psig), and has adequate capacity to maintain system pressure for at least. 3D days. j ( l 4.6.1.4.2 The containment' Channel Wald Pressurization System.shall he. demon- l strated DPERABLE at 'least once per 31 days by verifying that the system is ' pressurized ~ to greater than or equal to P,, [20 psig], and has adequate capacity to maintain system pressure for at least 30 days. 5 1 i i i 10 COMANCHE PEAK - UNIT 1 3/4 6-8B I
-Docket No. 50-445 August 14, 1987 CONTAINMENT SYSTEMS ,
INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION _ LCO 3.5 12 ( A) 3.6.1.5 Primary containment internal pressure shall be saintained between and psig. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:
- CowDt heeJs A4%
With the containment internal pressure outside .cf the limits above, restore the internal pressure to within the limits within 1 hour or be in atleast HDT STANDBY within the next 4 hours and in COLD SHUTDOWN within the following 30 hours. h SURVE1LLANCE REOUTREMENTS O - S R. 3. p, rt, t (M 4.6.1.5 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours. l l 1 4 CDMANCHE PEAK - UNIT 1 3/4 6-9B
i Secaet.No. 50-445 l
. August' 14, 1987 i CONTAINMENT SYSTEMS )
AIR TEMPERATURE i 1 LIMITING CONDITIDW FOR OPERATION l Ltc 3.r.-13CA) . 3.6.1.6 - Primary containment average air temperatum shall be' maintained:-
.a. Between and 'F in the containment upper compartment.'and
- b. Between and "F in the containment lower compartment., ;
APPLICABILITY . MDDES 1. 2. 3 and 4.
. ACTION: l 1
A ME 1 With the C.e u o e te o containment average air temperature vuot comfoTwing to the above i limits, restore the air temperature to within the limits within 8 hours or t>e i in at least HDT STANDBY within the next 6 hours and in IDLD SHUTDDWN within the fallowing 30-hours. ; 1
- k SURVEILLANCE REQUIREMENTS SR %F.0.1 DS 4.6.1.6.1 The primary containment upper compartment average air temp'erature a' shall be the arithmetical average of the temperatures at the following- -
locations: 2 Me<-A 4, 6ms 3 5.G IPQ . l Location a.
- b. 4]
l
~
- c. ,
.5a. 3.$ .ts . L (M <
4.6.1.6.2 The primary containment 1ower compartment.'everage air temperature 4 1 shall be the arittimetical average of the temperatures at the following locations:
. Meo o w B u e5 - 3.Ss G (A 1 Location ,
- a. ;
- b. _,
1
- c. >
The phiDocMtainment. fev- s)Dese &w4 att rIeMAS average temperatures shall be determined i 4 4.6.1.6.3 y j at least once per 24 hours. . COMANCHE PEAK - UNIT 1 3/4 6-10B l
i~n ic==Ied Ok dt. ~l ecd. SW (Sea Akh j) Decket No. 50-445 August .14, 1987 CONTAINMENT SYSTEMS I' CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDIT]DNTOR OPERATION 3.6.1.7 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance critaria in specification 4.5.1.7.
' APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION: With the structural integrity of the containment vessel not confaming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F. 1 SURVEILLANCE RE001REMENTS O 4.6.1.7 The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel. This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance of the surfaces or other abnormal degradation. Any abnormal degra-dation of the containment vessel detected during the above required inspec-tions shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2 within 15 days. e. O r0 COMANCHE PEAK - UNIT 1 3/4 6-11B __m_.._-.
its.as a red 0-< hide -1'eck y cc. (S~ee Akfe A Docket No. 50 445 C J u N+13 August 14, 1987 CONTAINMENT SYSTEMS a SHIELD BUILDING STRUCTURAL INTEGRITY l LIMITING CONDITION FOR OPERATION 3.6.1.8 The structural integrity of the shield building shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.8. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: With the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor trolant System temperature above 2DD*F. SURVEILLANCE REQUIREMENTS b v] 4.6.1.8 The structural integrity of the shield building shall be determined during the shutcown for each Type A containment leakage rate test (reference
.5 specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the shield building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal degradation. Any - abnormal degradation of the shield building detected during the above required inspections shal) he reported to the Comeission in a Special Report pursuant to Specification C.9.2 within 15 days.
e' COMANCHE PEAK - UNIT 1 3/4 5-12B
i l Socket slo. 50-445 !
. August.14, .1987 !
j CONTAINMENT SYSTEMS SHIELD BUILDING AIR CLEANUP SYSTEM l J L'IMITING CONDITION FOR OPERATION' b
/ c o -3.6./6
3.6.1.'9 . Two independent Shield Building Air Cleanup Systems shall be DPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4. 7CTION: Co#Dmos/s ' 4 at D - . 1 With one- Shield Building' Air Cleanup System inoperable, restore the inoperable system to OPERABLE status within 7 days or. be in at least'tCT STAND 8Y within the next 6 hours and in IDLD SHUTDOWN within the fol. lowing 30 Anura. SURVEILLANCE REQUIREMENTS : l 1
~
4.6.1.9 Each Shield Building Air Cleanup System shall be demonstrated DPERABLE: SR 3.5.M. l At least once per 31 d:ys on a STAGGERED TEST BASIS by initiating, a. from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the . system operates for at least 10 continuous hours with the heaters operating; . SPEcifiED wa'd oWPJ.sc.oqog suanot.i.swcss
- b. At least once per 18 months or (1) after any structural maintenance ,
on the HEPA filter or charcoal adsorber housings, or (2) following l painting, fire, or chemical release in any wantilation zone communi-cating with the system by:
^
. SR 3 5.4.2 dSR 1.5 4.3
,' ~ 1) Werifying that tho' cleanup system; satisfies the in place penetration and bypass leakage. testing acceptance critaria of q
- less than [*3% and uses the test procedure guidance in Regulatory 3
- Positions C.5.a. C.5.c. , and C.5.d of Regulatory Guide 1.52, .
" ' Revision 2, March 1978, and the system fisw rete-is I
cfa t 15; . ;
" SR 3.S.K.f Verifying, within 31 days after removal, that a laboratory a
i 2) analysis of a representative carbon sample obtained in accord-- ! ance with Regulatory Position C.6.b of Regulatory Guide'1.52, J r Revision 2, March 1978, meets the laboratory testing criteria
-of Regulatory Position C.6.a of Regulatory Guide 1.52 Revision 2, ;
March 1978, for a methyl iodide penetration of less than (""3%; and < SR 3.S.K.S
- 3) Verifying a system flow rate of cfm t 10% during system operation when tested in accordance with ANSI N510-1975. ,
f 3 l
!COMANCHE PEAK - UNIT 1 3/4 6-138 j
Docket No. 60-445 m - August 14, 1987 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- c. After eieYd0iours of charcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2 March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52 Revision 2. March 1978, for a methyl indice penetration of less than [**)%;
- d. At least once per 18 months by:
GR 3.5.4.S
- 1) Verifying that the pressure drnp across the combined HEPA
~
filters and charcoal adsorber banks is less than [6]: inches Water Gauge while apurating the system at a flow rate af cfm i 10%;
- 2) Verifyhnf'hbIbe system starts automatically on any Contain-ment Isolation test signal,
- 3) ' ' Veri [yfng daIihe filter cooling bypass valves can be manually opened sk s.s.a.9 Verifying that each system produces a negative pressure of 4) greater than er equal to [0.25] inch Water Gauge in the annulus within [1] minute after a start signal, and
- 5) verifykng '[tiak'(he heaters dissipate t kW when tested in accordance with ANSI N510-3 C 6 R 3. 5.4 .7,
- e. After each complete or partial replacement of a HEPA f'11ter bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than [*]% in
- accordance with ANSI N510-1975 for a DOP test aerosol while operating the system at a flow rate of cfm 210E; and
. S tl 3.'S./4.3 .
After~each complete or partial replacement of a 1:harcoal adsmtper bank, f. by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria ,of less than [*]% in accordance with ANSI N510-1975 for a halogenated hydrocarbon re #1gerant test gas while operating t.he system at a flow rate of cfm 2 10%.
~
APPLoc4&E Voftus.s hvcuoso ogswsowees/psuusswou
*0.05% value applicable when a HEPA filter or charcoal adsort>er efficiency of setSes 99% is assumed, or 1% when a HEPA filter or charcoal adsorber efficiency of 95% or less is assumed in the NRC staff's safety evaluation. (Use the value '
assumed for the charcoal adsorber efficiency if the value for the HEPA filter is different from the charcoal adsorber efficiency in the NRC staff's safety evaluation).
**Value applicable will be determined by the following equation:
P= , when P equals the value to be used in the test requirement (%), E is efficiency assumed in the SER for methyl iodide removal (%), and SF is the safety factor to account for charcoal degradation between tests (5 for systems with heaters and 7 for systems without heaters). v/ COMANCHE PEAK - UNIT 1 3/4 6-148
Socket No. 50-445- l August 14, 1987 r - CONTAINMENT SYSTEMS
,/
j CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.L 10 Each containment purge supply and exhaust isolation valve shall be -i OPERABLE and:
/.1 DEF/MTt CNS- CONT 4/A/HJ~AIT MNTEGhtryy %-fem C. i T Each [4 Finch] containment shutdown purge supply, and exhaust isola- ;
tion valve shall be closed and sealed closed, and
]
& ! bEFNJtTronS~ couT4MMEA!T ' ~1NY29417n .fheAny 4~
- b. The [8-inch:* containment surp T1y and exhaust' isolation valve (s) may be open for up to [100)] tours during a calendar yearj,neviced no more than one pair (one supply and one exhaust) afa apen at one i time, MODES 1, 2, "J, and 4. N F 4CO 3 5~ /, y APPLICABILITY:
h4~d:.M 265- :- j ; ACTION: t oo 3. i~ / Ct Db/TIONS 4. ed B~. . ,! l
- a. With a [42-inch] containment purge supply and/or exhaust isolation p valve open or not sealed closed, close and seal that valve or isolate i the penetrations (s) within 4 hours, otherwise be in at least HOT. l STANDBY within the next 6 hours and in COLD SHUTDOWN within the fol- ,
l lowing 30 hours. -
- b. With the [8-inch]* containment pu'rge supply and/or exhaust isolation ;
l valve (s) openlfor more than [1030]^ hours during a calendar year, K i close the open LB-inchy valvels) or isolate the penetration (s) l within 4 hours, otherwise be in at least HOT STAND 8Y within the next l i
.6 hours, and in COLD SHUTDOWN within the following 30 hours.
'I l SR 3 5" /.3~ (see AkkT)
With a containment purge supply and/or exhaust isolation valve (s) c. having.a measured leakage rate in excess of the limits of Specifi- ~ I -
~ cations 4.G.I.10.3 and/or 4.6.1.10.4 restore the inoperable valve (s) ;
I - to OPERABLE status within 24 hours, otherwise be in at least HOT { l STANDBY within the next 6 hours, and in COLD 4 HUT 00WN within the q following 30 hours. , j
*For a 3-inch valve or less, the valves may be open continuously. For an I
8-inch valve or less, the valves any be open for up to 1000 hours during a a calendar year. For an 18-inch valve or less, the valves may be open for up to l 500 hours during a calendar year. For a valve greater than 18 inches, the valve *' may be open for up to 250 hours during a calendar year. All valves that may be open during plant operations (MODE 1, 2, 3. or 4) must be qualified to close D under postulated accident conditions. After operational experience, the licen-see may request additional time fcr the qualified valves to be open during [ - plant operations and shall provide justification for the requested additional time as stated in the Bases. COMANCHE PEAK - UNIT 1 3/4 6-158
Socket elo. 50-445 ugust 14, 1987 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS
/. /. 2)EF/Nirt cAIS- coa!T4Ml!!?rNT %A/T2G4/~ry., [ fem C. 8 4.6.1.10.1' The [42-inch] containment purge supply and exhaust isolation valves
.). hall be verified to be sealed closed at least once per 31 days.
be /eM ser L en ?. r. / Tu rfficds% .Wem C i 4.6.1.10.2 The cumulative time that the [8-inch] purge . supply and exhaust 1 i isolation valves have been open during a calendar year shall be determined at least once oer 7 days. 3 J i ZA 3.$~ /.fAt 4.6.1.10.3 (See A4konce least g) 184 perdays on e STAGGERED TEST SASIS, the .inboaras 1 and outboard valves with resilient material seals in each sealed closed [42-inch) containment purge supply and exhaust penetration shall be demon- ' strated DPERABLE by verifying that the measurwd leakage rata is less than [0.05) L, when pressurized to P,. 4 4.6.1.10.4 At least once per 32 tiays months each IB-hch) rents % ment purge supply and exhaust isolation valve with resilient material seals shall be l demonstrated OPERABLE by verifying that the measured laakage rata is last than to [0.01) L, when pressurized to P,. f r I
\
b 1 i I 1 l i 1 if k s I
)
COMANCHE PEAK - UNIT 1 3/4 6-16B
1 Socket No.-50-445 August 14,;1987 1 CONTAINMENT SYSTEMS l q
..1-3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM.[ Credit taken for iodine removal] ..
l LIMITING CONDITION FOR OPERATION 1
- i co 3.5.3 A )
3.6.2.1 Two independent containment Spray Systems shall tw OPERABLE with each j Spray System capable of taking suction from the WST and transferring suction ! to the containment sump.
, APPLICABILITY: . MODES 1, 2, 3, and 4.
j ACTION: . . co@iTIDW R AND GONbtTIBM 'b i With one Containment Spray System inoperable, vestore the inoperable 51may - 1 ' System to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the inoperable Spray System to OPERABLE status within the next 48 hours or be in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated DPERABLE: .
-- S A 3. 5. 3.1
- a. At least once per 31 days by verifying that each valve (sanual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; s R 3.5.3.2 b - By verifying, that on-recirculation flow.~ each pump doweisps a J discharge pressure of greater than er equal to psig when-itested pursuant to Specification 4.0.5; !
- S R 3 5.3.3
- c. a At least once per.35.monthcLduring shutdown, by:
- 1) Verifying that each automatic valve in the flow path' actuates to its correct position on a test signal, and
' ' 2) Verifying that each spray pump starts automatically on a test signal.
- 3. 5~. 3. 'f
- d. At least once per 5 years by performing an air or smoke flow test
.through each spray header and verifying each spray nozzle is unobstructed.
k ( s YCOMANCHE PEAK - UNIT 1 3/4 6-17B-
- Socket No. 50-445 )
August' 14,1987 l CONTAINMENT SYSTEMS J
\~
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT. SPRAY , SYSTEM [No credit taken for iodine . removal] ,3
' LIMITING ~ CONDITION FOR OPERATION f 1.C. O 3 . 6 .~5 A 3.6.2.1 Two-independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST.and transferring suction to the containment sump. a l- APPL 7CABILITY: MODES 1, 2, 3, and 4.
AC ION: SEE NOTE 7 l
- a. With one Containment Spray System inoperable and at'least Ifour] .j containment cooling fans OPERABLE, restore the inoperable Spray '
System to DPERABLE status within 7 days or be in at least HDT STANDBY ~ within the next 6 hours and in CD1D SHUTDOWN within the foll.owing 30 hours. With two Containment Spray Systems inoperable and at least Ifour] ' ['N t b. containment cooling fans OPERABLE, restore at least one Spray System to OPERABLE status within 72 hours or be in at least HDT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restore both Spray Systems to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next}}