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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20155F4501998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Function Into Two New Functions in ITS Table 3.3.17-1 ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits ML20155F9551998-10-30030 October 1998 Proposed Tech Specs Pages to LAR 245,changing Methodology for Sf Pool B Criticality Analysis ML20154P3101998-10-16016 October 1998 Proposed Tech Specs Resolving USQ by Leaving Valves DHV-34 & DHV-35 Normally Closed ML20154C1581998-09-30030 September 1998 Proposed Tech Specs Pages Re LAR 238,to Correct RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR ML20238F4761998-08-31031 August 1998 Proposed Tech Specs,Proposing New Repair Process for Plant OTSGs ML20151X0431998-08-31031 August 1998 Proposed Tech Specs Adding Three Addl Reg Guide 1.97 Type a Category 1 Pami Variables & One Type B Category 1 Pami Variable to ITS Table 3.3.17-1, Pami ML20236V8831998-07-30030 July 1998 Proposed Tech Specs Pages Re CREVS & Ventilation Filter Test Program ML20236E9851998-06-30030 June 1998 Proposed Tech Specs Re Exigent License Amend Request 228,rev 1 for Once Through SG Tube Surveillance Program ML20249B2671998-06-18018 June 1998 Proposed Tech Specs Pages Re one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG Tubes ML20247P8931998-05-22022 May 1998 Proposed Improved Tech Specs 5.2.1 Re Onsite & Offsite Organizations ML20217P5181998-04-28028 April 1998 Proposed Tech Specs Re Reactor Coolant Pump Motor Flywheel Insp ML20217G0121998-04-23023 April 1998 Proposed Improved Tech Specs Section 5.7.2, Special Repts, Clarifying That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure) ML20217C6341998-03-20020 March 1998 Proposed Tech Specs Re Editorial Changes to Improved TS Saftey Limits & Administrative Controls to Replace Titles of Senior Vice President,Nuclear Operations & Vice President, Nuclear Production W/Position of Chief Nuclear Officer ML20217C4931998-03-20020 March 1998 Proposed Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp ML20203D1611998-02-20020 February 1998 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS ML20198S9151998-01-22022 January 1998 Proposed Tech Specs Consisting of Rev 1 to TS Change Request 210,correction of Typo & Addition of Footnotes ML20202G8511997-12-0505 December 1997 Proposed Tech Specs Establishing New Improved TSs (ITS) Surveillance Requirement for Performance of Periodic Integrated Leak Test of Cche Boundary & Revising ITS Bases 3.7.12 to Define Operability of Cche ML20202G7991997-12-0505 December 1997 Proposed Tech Specs Revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal ML20199G8461997-11-21021 November 1997 Proposed Tech Specs Pages Involving Additional Restrictions, Editorial Clarifications & Typos ML20212F2741997-10-31031 October 1997 Proposed Tech Specs Pages Re Decay Heat Removal Requirements in Mode 4 ML20212C9801997-10-25025 October 1997 Proposed Tech Specs Re Power Operated Relief Valve Lift Setpoint TS Limit That Has Been Revised for Instrument Uncertainty ML20217F5231997-10-0404 October 1997 Proposed Tech Specs Pages Addressing Revision to Description of Electrical Controls for Operating Reactor Building (RB) Recirculation Sys fan/cooler,AHF-IC,as Discussed in FSAR & Improved TS ML20217D2741997-10-0101 October 1997 Proposed Tech Specs Adding Methodology to Monitor first-span Intergranular Attack (Iga) Indications & Disposition Growth During Future B OTSG Eddy Current Exams ML20210T9771997-09-12012 September 1997 Proposed Tech Specs Replacement Pages Re New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys ML20216F8481997-09-0909 September 1997 Proposed Tech Specs Re Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR ML20217Q2121997-08-26026 August 1997 Proposed Tech Specs Changing Design Basis of EDG Air Handling Sys ML20217N2501997-08-20020 August 1997 Proposed Improved Tech Specs 5.6.2.10 Re Tube Surveillance ML20210K8921997-08-16016 August 1997 Proposed Tech Specs 3.8.1.3,requesting one-time Outage on Each EDG to Perform Necessary Mod & Maint ML20151L7541997-08-0404 August 1997 Proposed Tech Specs Extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified ML20196J1431997-07-29029 July 1997 Proposed Tech Specs Adding EDG Kilowatt Indication to post- Accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt ML20196H0281997-07-18018 July 1997 Proposed Tech Specs Changes Establishing Requirements for Low Temperature Overpressure Protection Sys ML20148K7811997-06-14014 June 1997 Proposed Tech Specs Re Efw,Hpi,Emergency Feedwater Initiation & Control Sys ML20138H8781997-05-0101 May 1997 Proposed Tech Specs Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J,Option B ML20137X5361997-04-18018 April 1997 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 ML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20212C0991999-08-31031 August 1999 Criticality Safety Analysis of Crystal River Unit 3 Pool a for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement with Water Holes ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20206S7561999-02-28028 February 1999 Rev 2 to Pressure/Temp Limits Rept, Dtd Feb 1999 ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 1999-09-02
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bh bjjulj djj ij b CRYSTAL RIVER-UNIT 3 6-2 800627 OM]
52 PRESIDENT I
SEN!OR VICE PRES. SENIOR VICE PRES.
ENGINEERING CORPORATE SERVS.
8 CONSTRUCTION 8 GEN. COUNSEL j VICE PRESIDENT VICE PRESIDENT POWER ENVIRONMENT PRODUCTICN & NEW TECHNOLOGY DIRECTOR ENVIRONMENTAL &
LICENSING AFFAIRS MANAGER ASST.VICE PRESIDENT PRODUCTION NUCLEAR SERVICES OPERATIONS NUCLEAR PLANT MANAGER MANAGER M.lCLEAR SUPPORT SERVICES NUCLEAR PLANT STAFF l
FIGURE 5.1 1 ORGANIZATION FOR IMPLEMENTING ENVIRONMENTAL TECHNICA L SPECIFICATIOh S .
5-4 PRESIDENT SENIOR SENIOR VICE PRESIDENT NUCLEAR VICE PR Ee : DENT ENGINEERING GENERAL REVIEW CORPORATE SERVICES
& CONSTRUCTION COMMITTEE 8 GENERAL COUNSEL VICE PRESIDENT PLANT VICE PRESIDENT POWER REVIEW ENVIRONMENT PRODUCTICN COMMITTEE &
NEW TECNNOLOGY ASST. VICE PRESIDENT DIRECTOR NUCLEAR OUALITY '
OPERATIONS PROGRAMS !
l l
l l
l FI G. 5.3 -1 ORGANIZATION FOR INDEPENDENT REVIEW AND AUDIT.
ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Plant Review Committee shall:
- a. Recommend to the Nuclear Plant Manager written approval or disapproval of items considered under 6.5.1(a) through (d) above.
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(3) through (e) above constitutes an unreviewed safety question.
- c. Provide written notification within 24 hours to the Assistant Vice President, Nuclear Operations and the Nuclear l General Review Committee of disagreement between the PRC and the Nuclear Plant Manager; however, the Nuclear Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The Plant Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Assistant Vice President, l Nuclear Operations, and Chairman of the Nuclear General Review Committee.
6.5.2 NUCLEAR GENERAL REv'!EW COMMITTEE (NGRC)
FUNCTION 6.5.2.1 The Nuclear General Review Committee shall function to provide independent review and audit of designated activities in the areas of:
- a. Nuclear powt.r plant operations
- b. Nuclear engineering
- c. Chemistry and radiochemistry
- d. Metallurgy
- e. Instrumentation and control
- f. Radiological safety
- g. Mechanical and electrical engineering <
- h. Quality as.urance practices CRYSTAL RIVER - UNIT 3 6-7
ADMINi3TRATIVE CONTROLS RECORDS 6.5.2.11 Records of NGRC activities shall be prepared, approved and dis-tributed as indicated below:
- a. Minutes of each NRCC meeting shall be prepared, approved and forwarded to the Senior Vice President, Engineering and Con-struction, within 14 days following each aeeting.
- b. Reports of reviews encompassed by Secti.m 6.5.2.8 above, shall be prepared, approved and forwarded to the Senior Vice President, Engineering and Construction, within 14 days fol-lowing completion of the review.
- c. Audit reports encompassed by Section 6.5.2.9 above, shall be forwarded to the Senior Vice President, Engineering and Con-struction, and to the management positions responsible for the areas audited within 30 days after completion of the __ ._
audit.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
- a. The Commission shall be notified and/or a report submitted pursu-ant to the requirements of Specification 6.9.
- b. Each REPORTABli OCCURRENCE requiring 24-hour notification to the Commission shall be reviewed by the PRC and submitted to the NGRC and the Assistant Vice President, Nuclear Operations.
CRYSTAL RIVER - UNIT 3 6-11
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The facility shall be placed in at least HOT STANDBY within one hour.
- b. The Safety Limit violation shall be reported to the Commission, the Assistant Vice President, Nuclear Operations, and to the NGRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the Commission, the NGRC and the Assistant Vice President, Nuclear Operations, within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented, and asintained covering the activities referenced below:
- a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.
- b. Refueling operations.
- c. Surveillance and test activities of safety-reisted equipment.
- d. Security Plan implementation.
- e. Emergency Plan implementation.
- f. Fire Protection Program implementation.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PRC and approved by the Nuclear Plant Manager prior to implementation and reviewed periodically as set forth in administrative procedures.
CRYSTAL RIVER - UNIT 3 6 .
-p
5-1 5.0 ADMINISTRATIVE CONTROLS Objective To define the organization, assign responsibilities, describe the environmental surveillance procedures, provide for a re-view and audit function, and prescribe the reporting require-ments in order to insure continuing protection of the environ-ment and implement the Environmental Technical Specif1 cations.
5.1 ORGANIZATION The organization responsible for environmental protection, en-vironmental monitoring and the implementation of the Environ-mental Technical Specifications,for Crystal River Unit 3, is shown in Figure 5.1-1.
5.2 RESPONSIBILITY The responsibility for the conduct of the preoperational en-viiciimental ~ monitoring program described in Section 3 and special studies described in Section 4 is that of the Environ-ment and New Tecnnology Department under the direction of the Director of Environmental and Licensing Affairs. The
. responsibility for the conduct of the operational environmen-tal monitoring program and the implementation of Environmental Technical Specifications becomes the responsibility of the Power Production Department.
The plant organization is responsible for the development of Operating and Surveillance Procedures described generally in Section 5.5 and supplying field data to the Manager, Nuclear Support Services as required by Sections 2, 3, and 4 of the Environmental Technical Specifications.
The Manager, Nuclear Support Serv %es is responsible for con-sultant contracts, State and local regulatory agreements, assembly of data, preparation and review of reports required by Section 5.6 of these Environmental Technical Specifica-tivas, and making recommendations to improve environmental protection practices.
All reports and correspondence with the NRC regarding the En-vironmental Technical Specifications shall be approved and signed by the Assistant Vice President, Nuclear Operations.
The Nuclear Plant Manager shall, however, make reports by telephone and telegraph of any incident or occurrence requiring reporting within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less, as required in Section 5.6.
-9m .-Q,- -
.9. -a - - - - - -
5-5 5.4 ACTION TO BE TAKEN IF LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4.1 Imediate remedial actions as permitted by these environmental technical specifications shall be implemented until such time as the limiting condition for operation is met.
5.4.2 The occurrence shall be promptly reported ta the Chairman of the Nuclear General Review Committee and investigated as specified in Section 5.3.
5.4.3 The Nuclear General Review Committee shall prepare and submit a report for each occurrence in accordance with Section 5.3.10.
5.4.4 The Assistant Vice President, Nuclear Operations, shall report the occurrence to the NRC as specified in Section 5.6.2.
5.5 PROCEDURES 5.5.1 Explicit written procedures, including applicable check-off lists and instructions, shall be prepared for the implementa-tion of the monitoring requirements described in Sections 2 and 3, approved as specified in Section 5.5.2, and adhered to for operation of all systems and components involved in carry-ing out the effluent release and environmental monitoring pro-grams. Procedure shall include sampli.19, instrument calibra-ti on , analysis, and action to be taken when limits are approached or exceeded. Calibratior. frequencies and standards for instruments used in performing the measurements shall be included. Testing frequency of alarms shall be included.
These frequencies shall be determined from experience with i similar instruments in similar environments and from manufac- l turers' technical manuals. l 5.5.2 All procedures implemented by plant staff personnel described in Section 5.5.1 above, and changes thereto, shall be reviewed as specified in Section 5.3 and approved by the Nuclear Plant Manager prior to implementation. Temporary changes to procedures which do not change the intent of the original procedure may be made, provided such changes are approved by two members of the plant management staff, one of whom holds a Senior Operator's license. Such changes shall be documented, subsequently reviewed, and approved by tne Plant and Nuclear General Review Committees. All Procedures and changes to procedures utilized by contractors to implement the environ-mental and monitoring programs described in Section 3 shall be i reviewed and approved by the Manager, Nuclear Support Services.
TSCRN55(DN-65)
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