ML20199E687
| ML20199E687 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 01/29/1998 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20199E694 | List: |
| References | |
| NPF-37-A-099, NPF-66-A-099, NPF-72-A-090, NPF-77-A-090 NUDOCS 9802020230 | |
| Download: ML20199E687 (26) | |
Text
{{#Wiki_filter:. 4 a n:q k-A UNITED STATES g :p NUCLEAR REGULATORY COMMIS810N 4 l WASHINGTON, D.C. soseHotH g***** COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. NPF-37 1. -The Nuclear Regulatory Comniission (the Commission) has found that: A. The application for amendment by Commonwealth Edison Company (the licensee) dated June 17,1997, as supplemented by letters dated November 26,1997, and January P 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the he24th and safety of the public, and (ii) that such activities will be conducted in compliance with the Commisblon's regulations; D. The issuance of this amendment will not be inimical to the common defense and
- ecurity or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirerrants have been satisfied 4 Accordingly, the license is emended by changes to the Technical Specifications as indicated in the attachment to this license amcndment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows: 9802020230 900129 PDR ADOCK 05000454 p PDR
t (2) Technical SDecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 99 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The - licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days. The Containment Vessel Structural Integrity Program shall be implemented within 60 days of issuance of this amendment. FOR THE NtJCLEAR REGULATORY COMMISSION -U h 2 Geo . Dick, Seni Project Manager Project Directorate 1112 D: vision of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 29, 1998
o nog $* j[ UNITED STATES to B NUCLEAR RE2ULATORY CSMMISSION t! WASM;NGTON, D.C. 20eeH001 %...../ COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 l l BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 Ucense No. NPF 66 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Commonwealth Edison Company (the licens0e) dated June 17,1997, as supplemented by leters dated November 26, 1997, and January 9,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endungering the health and safety of the public, and (ii) l that such activities will be conducted in compliance with the Commission's l regulations; D. The issuance of this amendment wiil not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to i a Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating Lic.nse No. NPF-66 is hereby amended to read as follows:
~... b ( ' (2) Technical Specification 1 The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 99 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contsined in Appendix B, both of which were attached to License No. NPF 37, dated February 14,1905, are hereby incorporated into this license. Attachti snt 2 contains a revision to Appendix A which is hereby incorpor.ated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days. The Containment Vessel Structural Integrity Program shall be implementsd within 60 days of issuance of this amendment. FOR THE NUCLEAR REGULATORY COMMISSION Y& Geo . Dick, SeniorProject Manager Project Directorate 111-2 Division of Reactor Projects - lil/IV office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 29, 1998 A f t
c o ( ATTACHMENT TO LICENSE AME.NDMENT NOS. 99 AND 99 FACILITY OPERATING LICFdSE NOS. NPF-37 AND NPF-86 DOCKET NOS. STP150-454 AND STN 50315 Revise the Appendix A Technical Specifications by removing the pages identified below and Irterting the attacheo pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Remove Pages incert Paaes N4 &3 W4 &3 3/4 6-8 3/4 6-8 3/4 6 9 3/4 6-9 3/4 6-10 3/4 6-10 B 3/4 6 2 B 3/4 3-2 6-20 6-20 6-20a 6-23 6-23 I
o 4 CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) b. The reporting requirements and frequency of Type A tests shall be in accordance with Regulatory Guide 1.163, September 1995, and 10 CFR 50, Appendix J, Option B. c. The accuracy of each Type A test shall be verified by a supplemental test conducted in accordance with Regulatory Guide 1.163, September 1995, a..d 10 CFR 50, Appendix J Option B. d. Type B and r tests ahall be conducted in accordance with Regulatory Guide 1.163, September 1995, and 10 CFR 50, Appendix J, Option D. e. Air locks shall be tested and demonstrated OPERABLE by the require-ments of Specification 4.6.1.3; f. Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.7.3 or 4.6.1.7.4, as applicable; and g. The structural integrity of the exposed accessible interior and exterior surfaces of the containment vessel, including the liner plate, shall be demonstrated during the shutdown for each Type A containment leakage rate test by r. visual inspection of these surfaces. This inspection shall be performed at a frequency in accordance with Regulatory Cuide 1.163, September 1995, to verify no apparent changes in appearance or other abnormal degradation. h. The provisions of Specification 4.0.2 are not applicable. BYRON - UNITS 1 & 2 3/4 6-3 AMENDMENT NO. 99 ? .a
CONTAINMENT SYSTitti i CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The containment shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: If containment is found to be inoperable, restore the containment to OPERABLE status within I hour or be at least HOT STANDBf within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE RE0VIREMENTS 4.6.1.6 Verify containment structural integrity in accordance with the Containment Vessel Structural Integrity Program. 4 e e BYRON - UNITS 1 & 2 3/4 6-8 AMENDMENT NO.99 4 ~ e ,w.
QQAffAIMalENT SYR1RMS ATATwueMT Vasant. 3TaucTumat. INTECRfiY t m t*huca amoufneuents fcentinuedi PAGE INTENTIONALLY LEFT BLAWK BYRON - UNITS 1 & 2 3/4 6-9 .MENDMENT NO. 99
_. _.. _.. _=. _.. _. _. _ _. - _ _ _..... --...._.._..._.______.._m. .m_.___..____..__. CONTAIMMENT SYSTEMA s i a QQNTAIMMENT VEAARL ATRUCTURAL INTEGRITY SURVEItfmuct R2001atutNTs fcentinued) 4 + 4 6 f n PAGE INTENTIONALLY LEFT BLANK BYMON - UNITS 1 & 2 3/4 6-10 ARENDMENT No.99
CONTAIMENT SYSTEMS BASES 3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial i temperature condition assumed in the accident analysis for a steam line break accident. Measurements shall be made at all of the listed running fan -locations, whether by fixed or portable instruments, to detr.rmine the average air tssperature. 3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGR11Y This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural Integrity is required to ensure that the containment will withstand the maximum pressure of P, in the event of a cold leg double-ended break accident. Surveiliance Requirement 4.6.1.6 ensures that the structural integrity of the containment will be maintained in accordance with the provisions of the Containment Structural Integrity Program. Testing and frequency are consistent with the requirements of 10 CFR 50.55a(b)(2)(vi), " Effective edition and addenda of Subsection IWE and Subsection IWL, Section XI," and 10 CFR 50.55a(b)(2)(ix), " Examination of concrete containments." Predicted tendon lift-off forces will be d; c::. mined consistent with the recommendations of Regulatory Guide 1.35.1, July 1990. 3/4.6.1.7 CONTAINMENT PURGE VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves are required to be sealed closed (power removed) during plant operations since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident. Maintaining these valves sealed closed during plant operation ensures that excessive quantities of radioactive material will not be released via the Containment Purge System. To provide assurance that the 48-inch containment valves cannot be inadvertently opened, the valves are sealed closed in accordance -with Standard Review Plan 6.2 ) which includes mechanical devices to seal or lock the valve closed, or prevents power from being supplied to the valve operator. The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves since, unlike.the 48-inch valves, the 8-inch valves are capable of closing during a LOCA or steam line break accident. Therefore, the SITE BOUNDARY dose guideline values of 10 CFR Part 100 would not BYRON - UNITS 1 & 2 B 3/4 6-2 AMENDMENT NO.99
.__._._~_._____m.-___._....__._, ,.. _ _ _ _ _. ~. _ _ _... _. _ _ _. afwf MiaTRATIVE naastant_a t l PhocRDURES AMD PROGRAMS fContinuedn 2) A Land Use Census to ensure that changes in the use of areas at and beyond the s!TE DOUNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and 3) Participation in a Interlaboratory comparison Program to ensure + that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. g, containment Vammal structural Intaarity Proaram This program provides controls for monitoring containment vessel structural integrity including routine inspectic'es and tests to identify degradation and corrective actions if degradaticn is found. The containment Vessel structurs! Integrity Program, inspection frequencies, and acceptance criteria shall be in accordance with 10 CFR 50.55a(b)(2)(vi), " Effective edition and addenda of subsection IWE and subsection IWL, section XI," and 10 CFR 50.55a(b)(2)(ix), " Examination of concrete containments," as modified by approved exemptions. Predicted tendon lift-off forces shall be determined consistent with the recommendations of Regulatory Guide 1.35.1, July 1990. In addition, Unit 1 may have sheathing filler grease voids in excess of 5% of the not duct volume 4 for up to 35 tendons until the end of 31R08. 6.9 REPORTING REQUIKEMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Fedesral Regulations, the following reports shall be submitted to the Regional Administrator of the NRC Regional Of fice unless otherwise noted. STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted followings (1) receipt of an Operating License, (2) amendment to the license involving a planned in:rease in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. 6.9.1.2 The startup Report shall address each of the tests identified in the Final safety Analysis Report F8AR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report. d O sYRON - UNITS 1 & 2 6-20 AMENDMENT NO. 99
ADNINISTRATIVR CONTROLB RdPORTING REQUIREMENTS (Continued] 6.9.1.3 startup Reports shall be submitted within: (1) 90 days following completion of :he startup Test Program, (2) 90 days following resumption or commencement of commercist power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup Report does not cover all three events (i.e., initial criticality, completion of startup Test Program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed. ANNUAL REPORTS 6.9.1.4 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each -year. The initial report shall be submitted prior to March 1 of the year. following initial criticality. BYRON - UNITS 1 & 2 6-20a AMENDMENT NO.99
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- ,-{d$fMMENT VISEEL STIUCTURAL INTEGRITY REPORT b.9.1.11 Any abnormal degradation of the containment structure detected during the tests required by the Containment Vessel Structural Integrity Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.
1 SPECIAL REPORTS i 6.9.2 special reports shall be submitted to the Regional Administrator of the NRC Reglonal-Of fice within the time period specified for each report. l 6.10 RECORD. RETENTION In addition to the applicable record retention requirements of Title 10, i Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. 6.10.1 The following records aball be retained for at least 5 years i a. Records and logs of unit operation covering time interval at each power level; b. Records and logs of principal maintenance activities, inspections, l repair and replacement of principal items of equipment related to nuclear safety; c. All REPORTABLE EVENTS; d. Records of surveillance activities, inspections, and calibrations required by these Technical specifications; e. Records of changes made to the procedures required by specification 6.8; f. Records of radioactive shipments; g. Records of sealed source and fission detector leak tests and results; and h. Records of annual physical inventory of all sealed source material of record. 6.10.2 The following records shall be retained for the duration of the unit Operating Licenses a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final safety Analysis Report; b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories; BYRON - UNITS 1 & 2 6-23 AMENDMENT NO. 99
ps toegk UNITED STATES f, NUCLEAR REEULATCRY CSMMISSION WAsNINeToN, D.c. Smee01 4
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l 4 COMMONWEALTH EDISON COMPANY DOCKET No. STN 50 456 5 BRAIDWOOD STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 f License No. NPF 72 j 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Commonwealth Eciison Company (the licensee) dated June 17,1997, as supplemented by letters dated November 26, l 1997, and January 9,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; l B. The facility will operate in conformity with the application,' the provisions of the Act, and the rules and regulations of the Commission; C. Titere is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's r regulations; 3 D. The issuance of this amendment will not be inimical to the common defense and l security or to the health and safety of the public; and 1 ~ E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated W1 the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF 72 is hereby amended to read as follows: i I k 4 4 i'... 6,-----_ .,--_%-m.,-g,w,,,_,._7 e,,, __,-,em,,_,,..n. ,.._._c,m,,_%,-m ,mm... .,-_,w- _.m-,,.,,._,m,-a ._m....,,,...._.,n.~m .-s,.__n._ --e-r
2 (2) Technical Specifications The Technical specifications contained in Appendix A as revised through Amendment No. 90 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical 6pecifications and the Environmental Protection Plan. 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days. The Containment Vessel Structural Integrity Program shall be implementc3 within 60 days of issuance of this amendment. FOR THE NUCLEAR REGULATORY COMMISSION ff George F. Dick, Senior roject Manager Project Directorate lll 2 Division of Reactor Projects. lllllV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance: January 29, 1998 I
aasog ,yv t UNITED STATES l 3 NUCLEAR REGULATORY COMMISSION = WASHINGTON, D.C. s06eH001 l COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50 457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i Amendment No. 90 l Ucense No. NPF 77 1. The Nucisar Regulatory Commission (the Commission) has found that: A. The application for amendment by Commonwealth Edison Company (the licensee) dated June 17,1997, as supplemented by letters dated November 26, 1997, and January 9,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not he inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to tnis license amendment, and paragraph 2.C.(2) of Facility Operating Ucense No. NPF.77 is hereby amended to read as follows:
t s 2-l (2) Technical Specifications The Technical Spegifications contained in Appendix A as revised through Amendment No. W and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF 72, dated July 2, 4 1%7, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of the date if its issuance and shall be implemented within 60 days. The Containment Vessel Structural Integrity Program shall ] be implemented within 60 days of issuance of this amendment. FOR THE NUCLEAR REGULATORY COMMISSION j i Of ( Geo F. Dick, Seni roject Manager Project Directorate 1112 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 29, 1998 i i i t + k .-.__..r-.--,. -,. - ~ ~ - - - ~.. -.,, - - .y r y-
ATTACHMENT TO LICENSE AMENDMENT NOS. 90 AND 90 FACILITY OPERATING LICENSE NOS. NPF 72 AND NPF 77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Appendix 'A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the area of change, Remove Paoes insert Panes 3/4 6-3 3/4 6-3 3/4 6-8 3/4 6-8 3/4 6 g 3/4 6 g 3/4 6-10 3/4610 B 3/4 6-2 B 3/4 6 2 6 20 6-20 6 20s 6 23 6 23
00NTAllMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b. The reporting requirements and frequency of Ty>e A tests shall be in accordance with Regulatory Guide 1.163, Septomser 1995, and 10 CFR 50, Appendix J Option B. c. _The accuracy of each Type A test shall be verified by a supplemental test conducted in accordance with Regulatory Guide 1.163, September 1995, and 10 CFL 50, Appendix J, Option B. d. Type B and C tests shall be conducted in accordance with Regulatory Guide 1.163, September 1995, and 10 CFR 50, Appendix J Option B. e. Air locks shall be tested and demonstrated OPERABLE by the require-ments of Specification 4.6.1.3; f. Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.7.3 or 4.6.1.7.4, as applicable; and g. The structural integrity of the exposed accessible interior and exterior surfaces of the containment vessel, including the liner plate, shall be demonstrated during the shutdown for each Type A containment leakage rate test by a visual-inspection of these surfaces. This inspection shall be performed at a frequency in accordance with Regulatory Guide 1.163, September 1995, to verify no apparent changes in appearance or other abnormal degradation, h. The provisions of Specification 4.0.2 are not applicable. I BRAIDWOOO - UNITS 1-& 2 3/4 6-3 AMENDMENT NO. 90 ~.
' CONTAINMENT VESSEL STRUCTURAL INTEGRITY .o ggjTINGCONDITIONFOROPERATION 3.6.1.6 The containment shall be OPERABLE. AP1.LICABILITY: MODES 1, 2, 3, and 4. AC11Dil If centainment is found to be inoperable, restore the cantainment to OPERABLE status within I hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.1.6 Verify containment structural integrity in accordance with the containment Vessel Structural Integrity Program. BRAIDWOOD - UNITS 1 & 2 3/4 6-8 AMENDMENT NO. 90
CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY SURVIILLANCE REQUIREMENTS f Cont 1. sued 1 PAGE INTENTIONALLY LEFT BLO K BRAIDWOOD - UNITS 1 & 2 3/4 6-9 AMENDMENT NO. %
-. _. _.~~ -.--- QQNTAIMMENT SYSTEMS ' '. e 00pTMMMENT VESSEL STRUCTURAL INTEGPITY l BURVRf t f amen menUf **M*MTB fcontinued) f PAGE INTENTIONALLY LEFT BLANK 3RAIDWooD - UNITS 1 & 2 3/4 6-10 AMENDK2NT No. 90 -,nm -a- ,,-rn-w .,.-r .-~,.- - --n, ,,-.,w..-- e. ,..w-, m. ,, - -,, - -. ~ w
COIITA111 MENT. SYSTEMS maata 3/4.6.1.5 mia TmmesmATuma The limitations on containment everage air temperature ensure that the overall cortainment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a steam line break accident. Measuremente shall be made at all of the listed running fan locatione, whether by fised or portable instrumente, to determine the average air temperature. 3/4.6.1.6 Wif"$8*MT Vtaakt-aTmDCTumAT. In somffY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design atandards for the life of the facility. structural integrity is required to ensure that the containment will withstand the maximum pressure of P, in the event of a cold leg double-ended break accident. surveillance Requirement 4.6.1.6 ensures that the structural integrity of the containment will be maintained in accordance with the provisions of the Containment structural Integrity Program. Testing and frequency are consistent with the requirements of 10 CFR 50.55a(b)(2)(vi), " Effective edition and addenda of subsection twE and suosection ZwL, section XI," and section 10 crA 50.55a(b)(2)(ix), " Examination of concrete containments." Predicted tendon lift-off forces will be determined consistent with the recommendations of Regulatory Guide 1.35.1, July 1990. 3/4.6.1.7 OQNTafMM*MT PURGE VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves are required to be sealed closed (power removed) during plant operatione since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident. Maintaining these valves sealed closed during plant operation ensures that excessive quantities of radioactive material will not be released via the containment Purge system. To provide assurance that the 48-inch contain-ment valves cannot be inadvertently opened, the valves are esaled closed in accordance with standard Review Plan 6.2.4 which includes mechanical davices to seal or lock the valve closed, or prevente power from being bupplisd to the valve operator. The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves since, unlike the 48-inch valves, the s-inch valves are capable of closing during a LocA or steam line break accident. Therefore, the SITE DOUNDARY does guideline values of 10 CFR Part 100 would not BRAIDWOOD - UNITS 1 & 2 5 3/4 6-2. AMENDMENT NO. 90
ADMINISTRATIVE CONTROLS l PROCEDURES AND PROGRAMS (Continued) 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SliE BOUNDARY are identified and that modificat~1ons to the monitori7g program are made if required by the results of this census, and 3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. g. Containment Vessel Structural Inteority Proaram This program provddes controls for monitoring containment vessel structural integr<ty including routine inspections and tests to found. y degradation and corrective actions if Jc radation is identif The Containment Vessel Structural Integri y Prog' ram, inspection frequencies and acce tance criteria s all be in accordance with 10 CFR,50.55a(Su) 2)(vi), " Effective edition and b addenda of Subsection IWE and section IWL Section XI " and as modified by(b)(2)(ix), " Examination of conc, rete contain,ments," 10 CFR 50.55a approved exemptions. Predicted tendon lift-off forces shall be determined consistent with the recommendations of Regulatory Guide 1.35.1, July 1990. In addition Unit 1 may have sheathing filler grease voids in excess af 5% of,the net duct volume for up to 35 tendons until the end of AIP07. 6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10 of Federal Regulations, the following reports shall be submitted to the, Code Regional Administrator of the NRC Regional Office unless otherwise noted. STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following: 1 receipt of an Operatino License, L2 amendment to the license involving a p(la)nned increase in power Tevel,d(3) uns) fuel that has a different design ur has been manufacture by a different fuel nuclear, therma (4) modifications that may have significantly altered the supplier, and l, or hydraulic performance of the plant. 6.9.1.2 The Startup Report shall address each of the tests identified in the Final Safety Analysis Report FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report. BRAIDWOOD - UNITS 1 & 2 6-20 AMENDMENT NO 90
i O ADAINISTRATIVE CONTROLS BEEQRTING REQUIREMENTS fContinued) 0.9.1.3 startup Reports shall be submitted within (1) 90 days following com-pletion of the startup Test Program, (2) 90 days following resumption or com-mencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup Report does not cover all three events (i.e., initial criticality, completion of startup Test Program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 enonths until all three events have been completed. ANNUAL REPORTS 6.9.1.4 Annual Reports covering the activities of the facility as described below for the previous eclendar year shall be submitted prior to March 1 of each year. BRAIDWOOD - UNITS 1 & 2 6-20a AMENDMENT No. 90
o' TIVE CONTROLS CONTAINMENT VESSEL STRUCTLfAAL INTEGRITY REPORT 6.9.1.11 Any abnormal degradation of the containment structure detected during the tests required by the Containment Vessel Structural Integrity Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken. SPECIAL REPORTS 6.9.2 Special repurts shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report. 6.10 RECORD RETENTION in addition to the applicable record retention requirements of Titla 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. 6.10.1 The following records shall be retained for at least 5 years: a. Records and logs of unit operation covering time interval at each power level; b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety; c. All REPORTABLE EVENTS; d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; e. Records of changes made to the procedures required by Specification 6.8; f. Records of radioactive shipments; g. Records of sealed source and fission detector leak tests and results; and I h. Records of annual physical inventory of all sealed source material of record. l 6.10.2 The following records shall be retained for the duration of the unit Operating License: a. Records and drawing changes reflecting unit design modifications l made to systems and equipment described in the Final Safety Analysis Report; l b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories; BRAIDWOOD - UNITS 1 & 2 6-23 AMENDMENT NO. 90 l l --}}