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| | ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) |
| | : 6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses. |
| | : 7. Verifying the pressure in all diesel generator air start receivers to be greater than or equal to 380 psig. |
| | : 8. Verifying the lube oil pressure, temperature and differential pressure across the lube oil filters to be within manufac-turer's specifications. |
| | : b. At least once per 31 days by visually examining a sample of lube oil from the diesel engine to verify absence of water. |
| | : c. At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to 1 hour by checking for and removing accumulated water from the fuel oil day tank. |
| | : d. At least once per 92 days by removing accumulated water from the fuel oil storage tanks. |
| | : e. At least once per 31 days by performing a functional test on the emergency load sequencer to verify operability. |
| | : f. At least once per 92 days and from new fuel oil prior to addition to the storage tanks by obtaining a sample in accordance with ASTM-D270-1975 and by verifying that the sample meets the following minimum requirements and is tested within the specified time limits: |
| | : 1. As soon as sample is taken or from new fuel prior to addition to the storage tank, as applicable, verify in accordance with the tests specified in ASTM-0975-77 that the sample has: |
| | a) A water and sediment ~ content of less than or equal to 0.05 volume percent. |
| | b) A kinematic viscosity @ 40 C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes or a Saybolt Second Universal (ssu) viscosity at 100 F of geater than or equal to 32 ssu but less than or equal to , |
| | 14o.1; r ssu. |
| | P c) A specific gravity as specified by the manufacturer as API gravity @ 60 F of greater than or equal to 28 degrees but less than or equal to 42 degrees. |
| | : 2. Within one week after obtaining the sample, verify an impurity level of less than 2 mg of insolubles per 100 ml. when tested in accordance with ASTM-02274-70. |
| | HOPE CREEK 3/4 8-5 8607300235 860724 PDR ADOCK 05000354 P PDR |
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| | ATTACHMENT II TECHNICAL SPECIFICATION 6.9.3 SPECIAL REPORTS Technical Specification 6.9.2 indicates that special reports shall be submitted to the NRC Region within the time frame specified for each report. This change would add Specification 6.9.3 specifying that violations of the fire protection program as described in the FSAR require the submittal of a Licensee Event Report (LER) within 30 days. |
| | On May 13, 1986 PSE&G requested the NRC to remove the fire protection program (FPP) requirements from the HCGS Technical Specifications with the issuance of the full-power operating license, thereby replacing surveillance test procedures with periodic test procedures. This request was made in accordance with the guidance provided in Generic Letter 86-10 and followed precedence set by the Cleveland Electric Illuminating Co. (CEI) for the Perry Nuclear Power Plant. HCGS License Condition 2.C.7 requires compliance with the FPP as specified; however, with the removal of the FPP elements from the Technical Specifications, there is no indication of what is reportable should the requirements of the FPP not be met. License Condition 2.F requires a 24-hour notification whenever a License Condition is not met (and in this case that would be License Condition 2.C.7); however, this requirement is unnecessary, overly restrictive and inconsistent with Item E of Generic Letter 86-10. PSE&G has reviewed a submittal by CEI dated June 18, 1986 and determined that the requested addition to the reporting requirements of Technical Specification 6.9 is also applicable to HCGS. The addition indicates that whenever the FPP is violated and that violation would have adversely affected the ability to achieve and maintain saf e shutdown in the event of a fire, an LER must be submitted to the NRC Regional Administrator within 30 days. Therefore, the attached HCGS Technical Specification 6.9.3 has been revised accordingly. |
| | |
| | 5 3 |
| | ADMINISTRATIVE CONTROLS SEMIANUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) |
| | The radioactive effluent release report to be submitted within 60 days after January 1, of each year shall also include an assessment of radiation doses to the likely most exposed MEM8ER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1. |
| | The radioactive effluents release shall include the following information for each class of solid waste (as defined by 10 CFR 61) shipped offsite during the report period: |
| | : a. Container volume, |
| | : b. Total curie quantity (specify whether determined by measurement or estimate), |
| | : c. Principal radionuclide (specify whether determined by measurement or estimate), ,, |
| | : d. Type of waste (e.g., spent resin, compact dry waste, evaporator bottoms), |
| | : e. Type of container (e.g., LSA, Type A, Type B, large Quantity), and |
| | : f. Solidification agent (e.g., cement, urea formaldehyde). |
| | The radioactive effluent release reports shall include unplanned releases from the site to the UNRESTRICTED AREA of radioactive materials in gaseous and liquid effluents on a quarterly basis. |
| | The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP), OFFSITE DOSE CALCULATION MANUAL (0DCM) or radioactive waste systems made during the reporting period. |
| | MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Pro-gram Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office no later than the 15th of each month following the calendar month covered by the report. ' |
| | SPECIAL REPORTS , |
| | 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report. |
| | nSeRT 1 = |
| | HOPE CREEK 6-20 |
| | |
| | .d INSERT FOR PAGE 6-20 6.9.3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire-shall be reported to the Regional Administrator of the Regional Office of NRC via the Licensee Event Report System within 30 days. |
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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
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
- 7. Verifying the pressure in all diesel generator air start receivers to be greater than or equal to 380 psig.
- 8. Verifying the lube oil pressure, temperature and differential pressure across the lube oil filters to be within manufac-turer's specifications.
- b. At least once per 31 days by visually examining a sample of lube oil from the diesel engine to verify absence of water.
- c. At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by checking for and removing accumulated water from the fuel oil day tank.
- d. At least once per 92 days by removing accumulated water from the fuel oil storage tanks.
- e. At least once per 31 days by performing a functional test on the emergency load sequencer to verify operability.
- f. At least once per 92 days and from new fuel oil prior to addition to the storage tanks by obtaining a sample in accordance with ASTM-D270-1975 and by verifying that the sample meets the following minimum requirements and is tested within the specified time limits:
- 1. As soon as sample is taken or from new fuel prior to addition to the storage tank, as applicable, verify in accordance with the tests specified in ASTM-0975-77 that the sample has:
a) A water and sediment ~ content of less than or equal to 0.05 volume percent.
b) A kinematic viscosity @ 40 C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes or a Saybolt Second Universal (ssu) viscosity at 100 F of geater than or equal to 32 ssu but less than or equal to ,
14o.1; r ssu.
P c) A specific gravity as specified by the manufacturer as API gravity @ 60 F of greater than or equal to 28 degrees but less than or equal to 42 degrees.
- 2. Within one week after obtaining the sample, verify an impurity level of less than 2 mg of insolubles per 100 ml. when tested in accordance with ASTM-02274-70.
HOPE CREEK 3/4 8-5 8607300235 860724 PDR ADOCK 05000354 P PDR
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ATTACHMENT II TECHNICAL SPECIFICATION 6.9.3 SPECIAL REPORTS Technical Specification 6.9.2 indicates that special reports shall be submitted to the NRC Region within the time frame specified for each report. This change would add Specification 6.9.3 specifying that violations of the fire protection program as described in the FSAR require the submittal of a Licensee Event Report (LER) within 30 days.
On May 13, 1986 PSE&G requested the NRC to remove the fire protection program (FPP) requirements from the HCGS Technical Specifications with the issuance of the full-power operating license, thereby replacing surveillance test procedures with periodic test procedures. This request was made in accordance with the guidance provided in Generic Letter 86-10 and followed precedence set by the Cleveland Electric Illuminating Co. (CEI) for the Perry Nuclear Power Plant. HCGS License Condition 2.C.7 requires compliance with the FPP as specified; however, with the removal of the FPP elements from the Technical Specifications, there is no indication of what is reportable should the requirements of the FPP not be met. License Condition 2.F requires a 24-hour notification whenever a License Condition is not met (and in this case that would be License Condition 2.C.7); however, this requirement is unnecessary, overly restrictive and inconsistent with Item E of Generic Letter 86-10. PSE&G has reviewed a submittal by CEI dated June 18, 1986 and determined that the requested addition to the reporting requirements of Technical Specification 6.9 is also applicable to HCGS. The addition indicates that whenever the FPP is violated and that violation would have adversely affected the ability to achieve and maintain saf e shutdown in the event of a fire, an LER must be submitted to the NRC Regional Administrator within 30 days. Therefore, the attached HCGS Technical Specification 6.9.3 has been revised accordingly.
5 3
ADMINISTRATIVE CONTROLS SEMIANUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)
The radioactive effluent release report to be submitted within 60 days after January 1, of each year shall also include an assessment of radiation doses to the likely most exposed MEM8ER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.
The radioactive effluents release shall include the following information for each class of solid waste (as defined by 10 CFR 61) shipped offsite during the report period:
- a. Container volume,
- b. Total curie quantity (specify whether determined by measurement or estimate),
- c. Principal radionuclide (specify whether determined by measurement or estimate), ,,
- d. Type of waste (e.g., spent resin, compact dry waste, evaporator bottoms),
- e. Type of container (e.g., LSA, Type A, Type B, large Quantity), and
- f. Solidification agent (e.g., cement, urea formaldehyde).
The radioactive effluent release reports shall include unplanned releases from the site to the UNRESTRICTED AREA of radioactive materials in gaseous and liquid effluents on a quarterly basis.
The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP), OFFSITE DOSE CALCULATION MANUAL (0DCM) or radioactive waste systems made during the reporting period.
MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Pro-gram Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office no later than the 15th of each month following the calendar month covered by the report. '
SPECIAL REPORTS ,
6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.
nSeRT 1 =
HOPE CREEK 6-20
.d INSERT FOR PAGE 6-20 6.9.3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire-shall be reported to the Regional Administrator of the Regional Office of NRC via the Licensee Event Report System within 30 days.
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