Proposed Tech Specs,Requesting Relocation of Turbine Rotor Insp Requirement to Hbrsep Ufsar,Section 10.2ML20149H985 |
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Site: |
Robinson |
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Issue date: |
12/27/1994 |
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From: |
CAROLINA POWER & LIGHT CO. |
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To: |
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Shared Package |
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ML14183A610 |
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References |
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NUDOCS 9501040179 |
Download: ML20149H985 (3) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20149H9851994-12-27027 December 1994 Proposed Tech Specs,Requesting Relocation of Turbine Rotor Insp Requirement to Hbrsep Ufsar,Section 10.2 ML20101G6311992-06-18018 June 1992 Proposed Tss,Adding LCO & Surveillance Requirements for Pressurizer Porvs,Per Generic Ltr 92-06 ML20238A5071987-08-17017 August 1987 Proposed Tech Specs Changing Expiration Date to 100731 ML20214K1701986-08-13013 August 1986 Proposed Changes to Tech Specs,Deleting Tech Spec 5.3.1.6 Re Amount of Enriched Fissionable Matl Allowed Onsite for Neutron Flux Monitoring Purposes ML14190A9071985-11-13013 November 1985 Proposed Tech Specs Deleting Requirements Re Maint of Highly Borated Water Inventory in Boron Injection Tank & Associated Heat Tracing Required to Maintain High Boron Concentration in Solution,Per Generic Ltr 85-16 ML20081B9181983-10-31031 October 1983 Proposed Radiological Effluent Tech Specs,Incorporating Requirements to Perform Audits of Emergency Preparedness Program & Security Plan ML19354C3911980-12-0303 December 1980 Proposed Revisions to Tech Specs Reflecting Changes & Additions to Plant as Result of NRC Required Fire Protection Sys Mods ML19345B9931980-12-0101 December 1980 Proposed Tech Specs 5.4 for Spent Fuel Storage ML19294B3041980-01-10010 January 1980 Corrected Page 4.1-10 of Tech Specs.Restores Item 16 Inadvertently Omitted When NRC Issued 791105 Anend 45 to DPR-23 ML19210C4141979-11-0707 November 1979 Amend to Tech Specs 6.0-6.8,reflecting Corporate Reorganization of Generation Dept 1994-12-27
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210V1491997-07-23023 July 1997 Rev 6 to Security Personnel Training & Qualification Plan ML20149H9851994-12-27027 December 1994 Proposed Tech Specs,Requesting Relocation of Turbine Rotor Insp Requirement to Hbrsep Ufsar,Section 10.2 ML20044G6131993-05-11011 May 1993 Rev 5 to Design Guide DG-II.20, Design Guide for Civil/Structural Operability Reviews. ML20116D2961992-08-31031 August 1992 Rev 2 to Nuclear Generation Group Manual 305-05, Prioritization Process ML20044G6141992-07-31031 July 1992 Rev 0 to 92C1737A, Recommended Operability Review Criteria for Piping Sys Subj to Level D Svc Loadings for Carolina Power & Light Nuclear Stations. ML20101G6311992-06-18018 June 1992 Proposed Tss,Adding LCO & Surveillance Requirements for Pressurizer Porvs,Per Generic Ltr 92-06 ML20090A4521991-07-30030 July 1991 Rev 7 to Hb Robinson Steam Electric Plant,Unit 2 Odcm ML20236B5051987-10-0606 October 1987 Plan for Annual Emergency Exercise at Hb Robinson Nuclear Power Plant - 871006 ML20238A5071987-08-17017 August 1987 Proposed Tech Specs Changing Expiration Date to 100731 ML20214K1701986-08-13013 August 1986 Proposed Changes to Tech Specs,Deleting Tech Spec 5.3.1.6 Re Amount of Enriched Fissionable Matl Allowed Onsite for Neutron Flux Monitoring Purposes ML20209B9781986-03-0606 March 1986 Rev 2 to Offsite Dose Calculation Manual ML20151R7901986-01-10010 January 1986 Rev 2 to Hb Robinson Unit 2,Cycle 11 Sar ML20209B9711985-11-20020 November 1985 Rev 1 to Offsite Dose Calculation Manual ML14190A9071985-11-13013 November 1985 Proposed Tech Specs Deleting Requirements Re Maint of Highly Borated Water Inventory in Boron Injection Tank & Associated Heat Tracing Required to Maintain High Boron Concentration in Solution,Per Generic Ltr 85-16 ML20087M9341984-01-18018 January 1984 Public Version of Rev 3 to Emergency Plan Implementing Procedure PEP-105, Emergency Control - General Emergency & Jm Felton 840322 Release Memo ML20079K8201983-12-13013 December 1983 Public Version of Revised Emergency Plan Implementing Procedures PEP-102, Emergency Control - Unusual Event, PEP-103, Emergency Control - Alert & PEP-104, Emergency Controls - Site Emergency ML20081B9181983-10-31031 October 1983 Proposed Radiological Effluent Tech Specs,Incorporating Requirements to Perform Audits of Emergency Preparedness Program & Security Plan ML20083H8681983-10-0606 October 1983 Public Version of Revised Emergency Plan & Procedures, Including Procedures PEP-001 Re introduction,PEP-351 Re Confirmation of Offsite Dose Projections & PEP-105 Re Emergency Control - General Emergency ML20077B9701983-06-14014 June 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures PEP-2.3 Re Emergency Control - alert,PEP-2.5 Re Emergency Control - General Emergency & PEP-2.6.21 Re Emergency Communication ML20076K4511982-11-0202 November 1982 Public Version of Corporate Emergency Plan Implementation Procedures,Including Procedures CEPIP-2 Re Emergency Response Team Transportation & CEPIP-3 Re Emergency Response Manager ML20063M4161982-07-29029 July 1982 Public Version of Revision 0 to Emergency Plan & Procedure PEP-2.6.20, Dose Projection Coordinator. Revision 6 to Emergency Plan & Procedures,Vol 13,table of Contents,Encl ML20063D3951982-07-0202 July 1982 Public Version of Revised Emergency Plan Procedures, Including Procedures PEP-2.1 Re Initial Emergency Actions, PEP-2.2 Re Emergency Control - Unusual Event & PEP-2.3 Re Emergency Control - Alert ML20054M3511982-05-24024 May 1982 Public Version of Revised Emergency Plan Procedures, Including Revision 3 to Procedure PEP-2.6.4 Re Radiological Control Director & Revision 4 to PEP-3.3.1 Re in-plant Monitoring & Surveys ML20049J2281982-02-20020 February 1982 Public Version of Revision 4 to Emergency Plan & Procedures Vol 13,consisting of Plant Operating Manual Vol 13,Book 2 ML20039F3941981-12-11011 December 1981 Public Version of Revision 3 to Emergency Plan Procedures, Vol 13,including Procedures 3.4.1 Re Initial Dose projections,3.4.2 Re Whole Body Dose Projections & 3.4.3 Re Thyroid Dose Projections ML20039A9061981-11-23023 November 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 2.3 Re Emergency Control - alert,2.6.2 Re Emergency Repair Director & 3.4.1 Re Initial Dose Projections ML20038A5721981-10-29029 October 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures PEP-2.6.16 Re Emergency Response manager,PEP-2.6.18 Re Technical Analysis & PEP-2.6.19 Re Radiological Control Manager ML19354C3911980-12-0303 December 1980 Proposed Revisions to Tech Specs Reflecting Changes & Additions to Plant as Result of NRC Required Fire Protection Sys Mods ML19345B9931980-12-0101 December 1980 Proposed Tech Specs 5.4 for Spent Fuel Storage ML19294B3041980-01-10010 January 1980 Corrected Page 4.1-10 of Tech Specs.Restores Item 16 Inadvertently Omitted When NRC Issued 791105 Anend 45 to DPR-23 ML19210C4141979-11-0707 November 1979 Amend to Tech Specs 6.0-6.8,reflecting Corporate Reorganization of Generation Dept ML19254E2401979-10-26026 October 1979 Cycle 7 Startup Physics Test Results. ML20085D2921972-12-0101 December 1972 Steam Generator Pressure Test 1997-07-23
[Table view] |
Text
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ENCLOSURE 6 ;
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 NRC DOCKET NO. 50-261/ LICENSE NO. DPR-23 .
REQUEST FOR TECHNICAL SPECIFICATIONS CHANGE ,
TURBINE ROTOR INSPECTION REQUIREMENT CHANGE -
TECHNICAL SPECIFICATIONS PAGE i
9 9501040179 941277 PDR ADOCK 05000:161 P PDR
TABLE 4.1-3 (Continued)
FREOUENCIES FOR EOUIPMENT TESTS Maximum Time '
Check Frequency Between Test
- 13. .TusMs. Is y cti:n lisus?l, F-su.fimr Every-five-years. 6 : r:
DL: Tauoli u; DELC7'ED
- 14. Fans and associated Fans functioning. Once per operating NA charcoal and Abso- Laboratory tests on cycle.
lute Filters for charcoal must show Residual Heat > 99% iodine removal.
Removal Compartments I'n-place test must (HVE-Sa and 5b) p.,. show 1 99% removal of polydispersed DOP particles by the HEPA filters and Freon by the charcoal filters.
- 15. Isolation Seal Functioning Each refueling shutdown NA Water System
- 16. Overpressure Functioning Each refueling shutdown NA Protection System
- 17. Primary Coolant Functioning 1. Periddic{ejkagetesting(a)(b)
System check on each valve listed valves in Table 3.1-1 shall be accomplished prior to entering reactor operation condition (1) after every time the plant is placed in the cold shutdown condition for refueling, (2) af ter each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the pre-ceding 9 months, (3) after maintenance, repair or replacement work is performed.
(a)To satisfy ALARA requirements, leakage may be measured indirectly (as froc the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.
(b) Minimum test differential pressure shall not be less than 150 psid.
(C}More than one valve may be tested in parallel. The combined leakage shall not exceed 5.0 gpm. Redundant valves in each line shall not be tested in series.
4.1-13 Amendment No. 83
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'~-.... .
TABLE 4.1-3 (Continued)
...__._._.__._..~FRE00ENCIES'FOR EQUIPMENT TESTS
"* Check Freauency Maximum Time ;
Between Test ,
- 13. Deleted 1
- 14. Fans.and Fans functioning. Once per operating NA associated Laboratory tests- cycle. ,
charcoal.and on charcoal must '
Absolute show a 99% iodine Filters for removal. In-place r Residual Heat test must show Removal l a 99% removal of '
Com)artments polydispersed 00P
-(HVE-Sa and 5b) 3 articles by the iEPA filters and :
Freon by the &. .
charcoal filters.
- 15. Isolation Seal Functioning Each refueling NA Water System shutdown
- 16. Overpressure Functioning Each refueling NA <
Protection shutdown '
System
-17. Primary Coolant Functioning 1. Periodic leakage System check
- valves p*esting"* on each
) valve listed in Table 3.1-1 shall be !
-accomplished prior to entering reactor :
operation condition !
(1) after every time the '
plant is placed in the .
cold shutdown condition !
for refueling. (2) after ;
each time the plant is !
placed in a cold s..atdown !
condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if !
testing has not been accomplished in the ,
preceding 9 months- l (3) after maintenance, repair or replacement i work is performed.
j
")
To satisfy ALARA requirements, leakage may be measured indirectly (as l
' from the performance of pressure indicators) if accomplished in i accordance with approved procedures and supported by computations showing
'that the method is capable of demonstrating valve compliance with the -)
leakage criteria. ;
"') i
") Minimum test differential pressure shall not be less than 150 psid. i More than one valve may be tested in parallel. The combined leakage ;
shall not exceed 5.0 gpm. Redundant valves in each line shall not be i tested in series. '
I 4.1-13 Amendment No.
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