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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203H9241997-12-11011 December 1997 Proposed Tech Specs Re ESFAS Instrumentation ML20210U6401997-09-15015 September 1997 Proposed Tech Specs Revising Pressure/Temp Limits, Overpressure Protection & Reactor Vessel Matl ML20140A6201997-05-27027 May 1997 Proposed Tech Specs Deleting References to Steam Generator Tube Sleeving & Repair That Will Not Be Used for Westinghouse Model D5 Steam Generators in Use at Catawba Unit 2 ML20140A6681997-05-27027 May 1997 Proposed Tech Specs,Removing Surveillance Requirement 4.7.13.3a.2 Which Specifies 112,320 Gallon Min Volume of Borated Water Be Available to Supply Standby Makeup Pump ML20141C2281997-05-0808 May 1997 Proposed Tech Specs Allowing Natural Circulation Testing in Mode 3 Following Steam Generator Replacement for Catawba Unit 1 ML20136G2471997-03-0707 March 1997 Proposed Tech Specs Re SGTR Evaluation ML20133E6801997-01-0303 January 1997 Proposed Tech Specs to Eliminate SI Signal on Low Steam Line Pressure.Unnecessary SI Actuation Causes Unnecessary Challenges to Plant Safety Sys,Unnecessary Thermal Transient & Increases Actuation Cycles ML20132F0631996-12-12012 December 1996 Proposed Tech Specs,Section 3/4.3.3.1,for Units 1 & 2 Clarifying Info Re Operation of Radiation Monitors for Plant Operations ML20134H3281996-11-0404 November 1996 Proposed Tech Specs to Licenses NPF-35 & NPF-52,eliminating During Shutdown Restriction for 18 Month Standby Shutdown Sys DG Insp TS Surveillance 4.7.13.1.c ML20113G4431996-09-21021 September 1996 Proposed Tech Specs 8.3 Re Onsite Power Systems ML20117K1011996-08-29029 August 1996 Proposed Tech Specs,Replacing 960516 Response to Concerns Re Proposed Changes for Diesel Starting Air Sys Surveillance Testing ML20116K4601996-08-0808 August 1996 Proposed Tech Specs 6.9.1.9 Re Listings of Core Operating Limit Methodologies ML20113C7201996-06-21021 June 1996 Proposed Tech Specs 3.9.6,revising Term Lifting Loads to Lifting Force Used in Manipulator Crane TS 3.9.6b.2 & Redefining Auxiliary Hoist Min Capacities ML20112G9961996-06-0606 June 1996 Proposed Tech Specs,Reflecting Separate Volumes ML20112F6311996-06-0505 June 1996 Proposed Tech Specs 3/4.6 Re Containment Systems & 3/4.6.1 Re Primary Containment Integrity ML20112A7571996-05-16016 May 1996 Proposed Tech Specs 3/4.8 Re Surveillance Requirements ML20101M4741996-04-0303 April 1996 Proposed TS 3/4.6.4.3 & Bases Re Hydrogen Mitigation Sys ML20101H6101996-03-15015 March 1996 Proposed Tech Specs Re Replacement of SGs ML20100P0521996-03-0404 March 1996 Proposed Tech Specs Re Rev to 10CFR50,App J Which Provided for Reduced Test Frequency for Qualified Containment ML20096E8611996-01-19019 January 1996 Proposed Tech Specs,Providing Approved Revs to TS 6.9.1.9 to Incorporate Anticipated Revs to TRs DPC-NE-3000P-A & DPC-3002-A ML20096E5951996-01-12012 January 1996 Proposed Tech Specs Re Containment Leak Rate Testing Requirements of 10CFR50 App J,Option B 1999-09-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included ML20195B4181999-05-18018 May 1999 Revised Pages to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206T0571999-05-0505 May 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual. with List of Effective Pages ML20206J4531999-04-22022 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206Q8741999-04-22022 April 1999 Revs to CNS Selected Licensee Commitments Manual,Including Page 5 of List of Effective Pages & Pages 1-11 to Chapter 16.9-13.With ML20206B1271999-04-15015 April 1999 CNS Selected Licensee Commitments Manual, List of Effective Pages ML20206C0391999-04-15015 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20204G2541999-03-16016 March 1999 Revised Pages to Catawba Nuclear Station Licensee Commitments Manual ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20205B1341999-03-11011 March 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20204E7271999-03-0808 March 1999 Chapter 16.5-2,page 1-3 to CNS Selected Licensee Commitments Manual. with List of Effective Pages ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20199H4061999-01-16016 January 1999 Revised CNS Selected Licensee Commitments Manual ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236P8671998-07-0606 July 1998 Updated Pages to Catawba Nuclear Station Selected License Commitments Manual ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20249B6221998-06-11011 June 1998 Revised Table of Contents for Chapter 16 of Selected License Commitments Manual ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20247Q9871998-05-11011 May 1998 Revised Chapter 16 to Selected License Commitment Manual ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR 1999-09-16
[Table view] |
Text
. .'; i ELECTRICAL POWER SYSTEMS
-- SURVEILLANCE REQUIREMENTS (Continued) 11)' Verifying'that the fuel transfer valve transfers. fuel from each j fuel storage tank to the day tank of each diesel via the in-stalled cross-connection lines;
- 12) Verifving that the automatic load sequence timer is OPERABLE with the interval between each load block within the tolerances given in Table 4.8-2; 13). Verifying that the voltage and diesel speed tolerances for the accelerated sequencer permissives are 92.5 1 1% and 98 + 1%,
tespectively, with a minimum time delay of 2 1 0.2 s;
- 14) Verifying that 'he following diesel generator lockout features prevent diesel , orator starting only when required:
a) Turning gear engaged, or b) Maintenance mode; and
~
- 15) Operating at greater than or equal to 5600 KW but less than or equal to 5750 KW for ong hour or until operating temperature has stabilized. Within 5 minutes after completing this test, perform Specificatior,4.8.1.1.2g.6)b).
, h. At least once per 10 years or after any modifications which could
- affect diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least 441 rpm in less than or equal to 11 seconds; and
- 1. At least once per 10 years by:
- 1) Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or its equivalent, and I
- 2) Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection N0 of the ASME Code at a test pressure equal to 110% of the system design pressure.
Performing tank wall thickness measurements. The resulting 3) data shall be evaluated and any abnormal degradation will be -
justified or corrected. Any abnormal degradation will be documented in a report to the Commiscion.
4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be reported in a Speci.e.1 Report to the Commission pursuant to Spec'fication 6.9.2 within 30 days. Reports of diesel generator failures shall include the inf9rma-tic: :ecommended in b gulatory Position C..i.b of Regulatory Guide 1.108, Revi- 1 i
sion 1, August 1977. If the number of failures in the last 100 valid tests 4
- f any diesel generator 0 13 P PNU a y au:15 r unit b ic) i greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.109, Revision 1, August 1977.
CATAWSA - UNITS 1 & 2 3/4 8-7
TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE NUMBER OF FAILURES IN NUMBER OF FAILURES IN LAST 20 VALIO TESTS
- LAST 100 VALIO TGSTS* TEST FREQUENCY
$1 14 At least once per 31 days
> 2** ) 5 At least once per 7 days
- Criteria for determining number of failures and rumber of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, but determined on a per diesel generator basis. For purposes of this schedule, only valid tests conducted af ter the completion of the praoperational test requirements of Regulatory Guide 1.108, Revision 1. August 1977, shall be included in the computation of the "last 20/100 valid tests."
For the purposes of determining the required test frequency, the previous test failure count may be reduced to zero if a complete diesel overhaul to like-new condition is completed, provided that the overhau17 including appro-priate post-maintenance operation and testing, is specifically approved by the manufacturer and if acceptable reliability has been demonstrated. The reliability criterion shall be the successful completion of 14 consecutive tests in a single series. Ten of these tests shall be in accordance with the routine Surveillance Requirement 4.8.1.1.a 4) and 4.8.1.1.2.a 5), four tests, in accordance with the 184-day testing requirement of Surveillance Requirements 4.8.1.1. 2. a 4) and 4.8.1.1. a 5). If this criterion is not satisfied during the first series of tests, any alternate criterion to be used to transvalue the failure count to zero requires NRC approval.
- The associated test frequency shall be maintained until seven consecutive failure-free demands have been performed and the number of failures in the last 20 valid demands has been reduced tolss than or equal to one.
- A one-time waiver to the requirement for performance of a complete diesel generator overhaul to like-new condition has been granted in order to rezero four failures of diesel generator 1A which occured on April 12. 1900, April 19, 1988, April 25, 1999 and May 5, 1908. These failures resulted from f aulty pressure sensors in the diesel generator pneumatic control system.
CATAWBA - UNITS 1 & 2 3/4 8-9
Attcchment 2
. Discussion, No Significant Hazards Analysis and Environmental Impact Statement I
\
1
DISCUSSION , NO SIGNIFICANT HAZARDS ANALYSIS AND ENVIRONMENTAL IMPACT STATEMFRT The proposed amendment would:
(1) Allow a one-time waiver to the requirement for a complete D/G overhaul to discount failures.
This waiver will be for pressure sensor problems disecvered on D/G 1A. ;
i (2) Change the counting of failures on the Diesel Generators (D/Gs) from a "per l nuclear unit basis" to a "per diesel generator basis" as stated in 4.8.1.1.3.
Each unit at Catawba Nuclear Station has two independent diesel generators manufactured by IMO Delaval, Incorporated. These D/Gs are used to provide an emergency standby source of power to the equipment required to safely shutdown the reactor in the event of a loss of offsito power. .
t i Each D/G is controlled by a separate 60 psi penumatic control system that will trip the engine when the setpoints of various parameters are reached. This process is achieved by the venting of sensors causing the pnuumatic shutdown logic board to initiate a shutdown signal. Trips are divided into Group 1 and Group II trips. Jroup II trips are locked out for a period of 60-90 seconds from engine start to allow time for certain engine parameters to reach their normal operating state. On an emergency start, all trips are blocked except lo lo lube
'; oil, overspeed and generator differential. Lo Lo lube oil trip is a Group II trip. It is blocked, even on an emergency start, for 60-90 seconds, then it is j activated. This blocking is obtained by use of the P3 pressure sensor which is
- in line with the lo-lo lube oil sensors. On an engine start, P3 is pressurized
] and blocked via port 9 of the logic board. This allows time for the lo lo lube 1 oil sensors to block and its tubing line to pressurize. This pressure should hold j P3 pressurized when port 9 pressure is lost after the 60-90 second lockout period is terminated. If proc 6ss pressure to P3 is not obtained or is lost P3 will
} vent and the engine will trip when the lockout period is over. ,
] All the sensors on the engine and P3 in the control panel are manufactured by !
California Controls Company. Inc. (Calcon). A total of sever of these sensors !
are of one parti >ular model #: Calcon B4400 (Delaval part # F-573-156). These
- sensors are used in the followin2 locations
- 3 lo lo lube oli trips, lo lube oil ;
trip, 2 turbo lube oil trips, and P3 pressure sensor.
i The last four valid failures of D/G 1A can be attributed to the failure of this l Calcon B4400 pressure sensor. These failures took place on April 12, 1988. April J 19, 1988, April 25, 1988 and May 5, 1988. More information relating to the
, specifics of these failures can be found in my May 25, 1988 letter.
i Following the May 5, 1988 failure, it was discovered that because of a tolerance j stack-up in the manuf acture of the sensor, the pressure sensing diaphragm can be i J held solid against the pressure head, thus creating a smaller surface area. This
) smaller surface area would require a much higher pressure to reset the sensor. '
i l 1
l t
1 l
O DISCUSSION NO SIGNIFICANT HAZARDS ANALYSIS AND ENVIRONME*lTAL IMPACT STATEMENT Calcon remanufactured the pres sure head on the new sensors to add an additional 1 1/8" diameter circular bore .030" deep, to provide a positive gap between the ,
head and the diaphragm. The new sensors have been stanped P/N B4400B to I distinguish them from the questionable sensors. All Calcon B4400 sensors were !
replaced on D/Gs lA, IB, 2A, and 2B with Calcon B4400B sensors.
Based on the discoveries made by Calcon, it is concluded that the 6th, 7th, 8th, .
and 9th valid failures within the last 100 valid starts on Unit 1A D/G are !
attributed to the same root cause inadequate design and manufacture of the !
Calcon Model B4400 pressure sensor. The inadequacies of the Calcon sensors was reported by IMO Delaval Inc. in acccrdance with 10CFR21 by letters dated April 29, 1988 and May 12, 1988. A thorough description of the failure of the Calcon ,
sensors and Duke Power's actions to ensure continued reliability of the diesel !
generators at Catawba was presented to Region II and NRR personnel in Atlanta, i Georgia on June 9, 1988. Since replacement of all the Calcon B4400 sensors with B4400B sonsors, no further valid failures of any of Catawba's D/Gs has occurref..
Sinco the May 5, 1988 failure, Diesel Generator IA has had 32 valid successful starts. All of these starts, except one, were conducted in accordance with the routine surveillance requirements 4.8.1.1.2.a.4) and 4.8.1.1.2.a 5). The remaining start was performed in accordance with 184-day testing requirement of i surveillance requirements 4.8.1.1.2.a.4) and 4.8.1.1.2.a 5). This testing demonstrates the reliability of diesel generator 1A since the changes were made to its pneumatic control system. I Thn proposed changes to Technical Specification 4.8.1.1.3 changes the reporting '
requirement from a per nuclear unit basis, to a per diesel generator basis. Test i failures are already determined on a per diesel generator basis as discussed in the footnote to Tabic 4.8-1. The purpose of this footnote to Table 4.8-1 is to {
avoid excessive testing of all diesel generators due to failures experienced on !
one diesel generator. The reporting requirement is being changed to a per diesel i generator basis to be consistent with the testing criteria, and to avoid the need i for a etual counting system, one for determining test frequency and one for l determining reports. The testing frequency determination assures that a i reliability of 95% is maintained.
l 10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would note t (1) Involve a significant increase in the probability or consequences of l an accident previously evaluated or (2) Crease the possibility of a new or different kind of accident from any l accident previously evaluated or '
(3) Involve a significant reduction in a margin of safety.
The proposed amendment to allow a one time waiver to discount failures associated with the Calcon pressure sensors does not involve a significant increase in the probability or consequences of an accident previously evaluated. If the four failures added as a footnote to Table 4.b-1 for D/G 1A are not counted towards
s t 0 DISCUSSION. NO SIGNIFICANT IIAZARDS ANALYSIS AND ENVIRONMENTAL IMPACT STATEMENT ;
determining the testing frequency for D/G 1A, then the test frequency would be "at least once per 31 days". Since the new pressure sensors have been tested, their installation was approved by the manufacturer and acceptable reliability of D/G 1A has been demonstrated, this amendment will not involve a significant increase in tha probability or consequences of an accident previously evaluated, i The proposed am idment should increase the reliability of the Diesel Generator lA since it will reduce the wear and tear on D/G 1A associated with frequent 1 testing.
l
! The proposed amendment to modify the reporting requirements does not involve a 1 significant increase in the probability or consequences of an sccident previously
] evaluated. The purpose of this amendment is to make the reporting requiremcnts l consistent with the testing requirements and to avoid having to keep up with one set of numbers for testing and another set for reporting.
Neither of the proposed changes will create the possibility of a new or different kind of accident from any accident previously evaluated. The change allowing discount of the four pressure sensor failures creates no new accident possibilities. The diesel generators will continue to function as before and there is no change to their function in mitigating design basis events. The change to the reporting requirements will not affect the operation of the diesel generators, therefore can not create any new or different kind of accident.
- Neither of the proposed changes will involve a significant reduction in a margin 1
of safety. No functional change is being made to the D/Gs. Tle new pressure ,
sensors installed have increased tha reliability of the D/Gs. Thorofore. '
allowing the testing frequency reduction will not involve a significant reduction l in any margin of safety. The change to the reporting requirements will not '
l affect the operation of the diesel generators, therefore can not create a !
j significant reduction in a margin of safety. l
( ;
Environmental Impact
]
j The proposed Technical Specification change has been reviewed against the 4
criteria of 10 CFR 51.22 for the environmental considerations. As shown above,
! the proposed change does not involve a significant hazards consideration, nor 1
) increase the types and amounts of effluents that may be released offsite, nor l I increase individual or cumulative occupational radiation exposures. Based on the l foregoing, the proposed Technical Specification change meets the criteria given in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirement for an l
- Environmental Impact Statcaent.
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