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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8181998-06-12012 June 1998 Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design ML20247K7381998-05-13013 May 1998 Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements ML20217P9351998-04-28028 April 1998 Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances ML20216F4541998-03-0606 March 1998 Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring ML20197H5941997-12-19019 December 1997 Proposed Tech Specs Pages,Revising TS Section 4.2.2, Terrestrial Ecology Monitoring, by Changing Wording to Include Completion of Salt Drift Monitoring Program ML20211M2401997-10-0303 October 1997 Proposed Tech Specs Pages Associated W/Slmcpr Changes ML20217D3761997-09-29029 September 1997 Proposed Tech Specs Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated ML20211F6201997-09-24024 September 1997 Proposed Tech Specs Section 3/4.5.1,adding Surveillance Requirement to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie-valves ML20211M2641997-08-26026 August 1997 Revised TS Bases Pages for Amend 101 to License NPF-57 ML20217Q6731997-08-26026 August 1997 Proposed Tech Specs,Requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20198H2471997-08-26026 August 1997 Proposed Tech Specs Implementing Conservative Safety Limit Min Critical Power Ratio for Plant Cycle 7 Core & Fuel Designs ML20217Q3081997-08-25025 August 1997 Proposed Tech Specs Re Ultimate Heat Sink Temp & River Water Level Limits ML20210P3471997-08-20020 August 1997 Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage ML20211M2531997-07-16016 July 1997 Sanitized Version of TS Page Changes Re SLMCPR ML20149G4301997-07-16016 July 1997 Proposed Tech Specs Implementing Appropriately Conservative Safety Limit Min Critical Power Ratio ML20141C1621997-06-19019 June 1997 Proposed Tech Specs Revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & to Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20140D2201997-05-30030 May 1997 Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments ML20141G8291997-05-19019 May 1997 Proposed Tech Specs Revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Issues Related Issues Documented in Hope Creek Corrective Action Program ML20137N6271997-04-0101 April 1997 Proposed Tech Specs 4.6.1.1, Primary Containment Integrity, TS 3/4.6.1.2, Primary Containment Leakage, TS 3/4.6.1.3, Primary Containment Air Locks & TS 4.6.1.5.1, Primary Containment Structural Integrity ML20137M5961997-03-31031 March 1997 Proposed Tech Specs,Representing Changes to TS 2.1.2,action a.1.c for LCO 3.4.1.1 & Bases for TS 2.1 ML20137M1331997-03-31031 March 1997 Proposed Tech Specs Revising TS to Improve Consistency Between TS & Plant Configuration,Operation & Testing & Completing Required CA to Resolve Discrepancies Identified in CA Program ML20135E8101997-03-0303 March 1997 Proposed Tech Specs 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.2 Re Isolation Actuation Instrumentation & 3/4.3.3 Re Emergency Core Cooling Sys Actuation Instrumentation ML20134M0921997-02-11011 February 1997 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20134B5511997-01-24024 January 1997 Proposed Tech Specs 3.1.3.5 Re Control Rod Scram Accumulators ML20132F1791996-12-11011 December 1996 Revised Tech Specs Re Changes to TS Bases B 3/4.3.1, Reactor Protection Sys Instrumentation, & B 3/4.3.2, Isolation Actuation Instrumentation ML20135D6851996-12-0404 December 1996 Proposed Tech Specs 3.1.3.5, CR Scram Accumulators, for Improvement & Clarifies Statement of 961025 Initial Request ML20134F3831996-10-25025 October 1996 Proposed Tech Specs 3/4.3.1,3/4.3.2 & 3/4.3.3 Re Reactor Protection Sys Instrumentation,Isolation Actuation Instrumentation & Emergency Core Cooling Sys Actuation Instrumentation ML20134F4311996-10-25025 October 1996 Proposed Tech Specs 3.1.3.5 Control Rod Scram Accumulators ML18102A2561996-07-12012 July 1996 Proposed Tech Specs Re Qualifications of Operations Manager ML18101B3831996-05-22022 May 1996 Proposed Tech Specs,Requesting Approval of Changes to QA Program 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20216E6201999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 14 to Table of Contents & Rev 10 to Attachments 6,7 & 9 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML20206T8941999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 12 to Table of Contents,Rev 8 to Attachment 8,Rev 8 to Attachment 7 & Rev 8 to Attachment 9 ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20206G2281999-03-31031 March 1999 Rev 18 to ODCM for Hope Creek Generating Station ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8181998-06-12012 June 1998 Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design ML20247K7381998-05-13013 May 1998 Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML20217P9351998-04-28028 April 1998 Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances ML20216F4541998-03-0606 March 1998 Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML20197H5941997-12-19019 December 1997 Proposed Tech Specs Pages,Revising TS Section 4.2.2, Terrestrial Ecology Monitoring, by Changing Wording to Include Completion of Salt Drift Monitoring Program ML20197H8511997-12-0808 December 1997 Rev 0 to IST Program Submittal Interval 2,Dec 21,1997 Through Dec 20,2006 ML20198J6431997-10-10010 October 1997 Rev 0 to 55-WP3/F43TB3-05, Weld Procedure ML20211M6121997-10-0707 October 1997 Cycle 4 Startup Physics Testing ML20211M2401997-10-0303 October 1997 Proposed Tech Specs Pages Associated W/Slmcpr Changes ML20217D3761997-09-29029 September 1997 Proposed Tech Specs Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated ML20211F6201997-09-24024 September 1997 Proposed Tech Specs Section 3/4.5.1,adding Surveillance Requirement to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie-valves ML20198H2471997-08-26026 August 1997 Proposed Tech Specs Implementing Conservative Safety Limit Min Critical Power Ratio for Plant Cycle 7 Core & Fuel Designs ML20217Q6731997-08-26026 August 1997 Proposed Tech Specs,Requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20211M2641997-08-26026 August 1997 Revised TS Bases Pages for Amend 101 to License NPF-57 ML20217Q3081997-08-25025 August 1997 Proposed Tech Specs Re Ultimate Heat Sink Temp & River Water Level Limits ML20198J6541997-08-20020 August 1997 Rev 3 to 55-PQ7001-03, Procedure Qualification Record ML20198J6501997-08-20020 August 1997 Rev 5 to WP3/F43TB3-05, Welding Procedure Specification ML20210P3471997-08-20020 August 1997 Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage ML20149G4301997-07-16016 July 1997 Proposed Tech Specs Implementing Appropriately Conservative Safety Limit Min Critical Power Ratio ML20211M2531997-07-16016 July 1997 Sanitized Version of TS Page Changes Re SLMCPR ML20141C1621997-06-19019 June 1997 Proposed Tech Specs Revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & to Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20140D2201997-05-30030 May 1997 Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments ML20141G8291997-05-19019 May 1997 Proposed Tech Specs Revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Issues Related Issues Documented in Hope Creek Corrective Action Program ML20137N6271997-04-0101 April 1997 Proposed Tech Specs 4.6.1.1, Primary Containment Integrity, TS 3/4.6.1.2, Primary Containment Leakage, TS 3/4.6.1.3, Primary Containment Air Locks & TS 4.6.1.5.1, Primary Containment Structural Integrity ML20137M1331997-03-31031 March 1997 Proposed Tech Specs Revising TS to Improve Consistency Between TS & Plant Configuration,Operation & Testing & Completing Required CA to Resolve Discrepancies Identified in CA Program 1999-09-30
[Table view] |
Text
.. . __-__--_______-_-__-_______
, Nut-N91166 IDIE 01rIK 10191-13 1
I TECHNI, CAL SPE(l1ElCAllON PAGES WITli PEN AND INK CHANGES The following Technical Specification for Facility Operating License No. NPF-57 are offected by thin licenso amendment request:
12shDiea1 SoggidpMr.LQD ERGE 6.2.2 6-2 6.3 6-6 ATTAQMNr 2 gg6150474920604 p ADOCK 05000354 PDR '
_- -_--------__--_-_---_A
hDMINISTRATIVECONTROLS UNIT STAFF (Continued)
- b. At least nne licensed Reac+or Operator shall be in the control *oom when fuel is in the reacto . In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator shall be in the control room;
- c. A Radiation Protection Technician
- shall be on site when fuel is in the reactor;
- d. ALL CORE ALTERATIONS shall be observed and directly suptrvised by either a licensed Senior Reactor Operator or licensed Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibilities during this operation; and
- e. Administrative procedures shall be developed and implemented to limit
[
- , D the working hours of unit staff who perform safety-related functions e.g., licensed Senior Reactor Operators, licensed Reactor Operators, h/[ f.
radiation pr *
- tion technicians, equipment operators, and key main-tenance per W The Operett b:4P JW % *ing Engineer, Senior Nuclear Shift pu Supervisort, NM Xf t hpervisors, and Senior Operating Super-vi r shall ho w o Mor reaccor operator license. The Nuclear Control Operators shall nold a reactor operator license.
Adeoube shift coverage shali be maintained without reutine hGavy u.e of over-time. The objective shall be to have operating personnel work a cominal** 40-hour week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periodsofshutdownforrefueling,majormaintenanceonmajorunitmodifications, on a temporary bcsis the following guidelines shall be followed:
- 1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time. -
- 2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 houis in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in ary 7 day period, all excluding shift turnover time.
- 3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnoser time.
- 4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shif t.
Any deviation from the above guidelines shall be authorized by the appropriate department manager, or higher levels of management, in accordance with estab-lished procedures and with documentation of the basis for granting the devia-tion. Controls shall be included in the procedures such that individual over-time shall be reviewed monthly by the General Manager-Hope Creek Operations or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.
- The Radiation Protection Technician may be unavailable for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to acconnodate unexpected absence, provided inveediate action is taken to fill the required position.
- The shift schedule is based upon a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift with a work week of either 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. l HOPE CREEK 6-2 Amendment No. 41,
t,
, NIR-N91166 IDPE QUIK IG 91-13 Ilmf,AT_FOR TECl!NICAL SPECIFICATION PAGL,ft-2
- g. The operations Manager shall moot one of the followings (1) }{old a SRO licenso, or (2) Have hold a SRO license for this or a similar unit (BWR).
ATTAONDir 2
1 ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall provide advisory technical support to the Senior Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The Shif t Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training
[Ajin the t
unitresponse andlayout, design and analysis of thethe including unitcapabilities for transients of instrumentation and accidents,and and in Y fcontrolsinthecontrolroom. pd me oee n n ,s rwye< as wee;7te g
$4 y ,y 6.3 UNIT STAFF QUALIFICATIONS M Spec t /la NM 6 . 32.
- 6.3.1 Each member of the unit staf f shall meet or exceed the minimum qualifica-i f./ tions of ANSI /ANS 3.1-1981 f comparable positions, except for the Radiation
@g, Protection Manager who shall meet or exceed the qualifications of Regulatory 7 Guide 1.8, September 197 7 The licensed Reactor Operators and Senior Reactor Operators shall also meet or exceed the minimum qualifications of the supple-mental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC-letter to all licensees.
) y G.3.z
/p 6.4 TRAINING P/ / p 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager-Nuclear Training, shal! meet g'se or exceed the requirements and recommendations of Section 5.5 of ANSI /ANS 3.1-1981
,, and Appendix A of 10 CFR Fart 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licen-sers, and shall include f amiliarization with relevant indue.try operational experience.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Site Protection and shall meet or exceed the require-merts of the SRP (NUREG-0800) Section 13.2.2.11.6, 10 CFR 50 Appendix R and Branch Technical Position CHEB 9.5.1, Section C.3.d.
6.5 REVIEW AND AUDIT a 6.5.1 STATION OPE _ RATIONS REVIEW COMMITTEE (SORC)
FUNCTION 6.5.1.1 The 50RC shall function to advise the General Manager - Hope Creek Operations on all matters related to nuclear safety.
HOPE CREEK 6-6 s
, NIR-1191166 IlOIE OtEEK ICR 91-13 H{ SERT FOR TEClillICAL SPECIFICATIOli PAGE 6-6 6.3.2 The Operations Manager shall noot one of the following:
(1) lloid a SRO license, or (2) llave hold a SRO licenso for this or a similar unit (BWR).
e ATTAQMDIT 2 i
4