Proposed Tech Specs Re Internal Corrosion of Diesel Generator Fuel Oil Storage TanksML20101E456 |
Person / Time |
---|
Site: |
Catawba |
---|
Issue date: |
12/21/1984 |
---|
From: |
DUKE POWER CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20101E436 |
List: |
---|
References |
---|
NUDOCS 8412260259 |
Download: ML20101E456 (5) |
|
|
---|
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
A ,
0 ELECTRICAL p0WER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) during this test. Within 5 minutes after completing this 24-hour test, perform Specification 4.8.1.'1.2g.6)b);*
- 8) Verifying that the auto-connected loads to each diesel generator do not exceed ^" ; " _
_ i -- : kW; 6760
- 9) Verifying the diesel generator's capability to:
a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power, b) Transfer its loads to the offsite power source, and c) Se restored to its standby status.
- 10) Verifying that with the diesel generator operating in a test mode, connected to its bus, a simulated Safety Injection signal overrides the test mode by: (1) returning the diesel generator
- to standby operation, and (2) automatically energizing the emergency loads with offsite power;
- 11) Verifying that the fuel transfer valve transfers fuel from each fuel storage tank to the day tank of each diesel via the in-stalled cross-connection lines;
- 12) Verifying 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% and 98 + 1%,
respectively, with a minimum time delay of 2 0.2 s; and
- 14) Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:
a) Turning gear engaged, or b) Maintenance mode. j l
- If Specification 4.8.1.1.2g.6)b) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test. Instead, the diesel generator may be operated at greater than or equal to 5600 kW but less than or equal to 5750 kW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or until operating temperature has stabilized. l
~
8412260259 841221 PDR ADOCK 05000413 P PDR CATAWBA - UNIT 1 3/4 8-6
4
- - c 1.c
.3 ' ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continue )
0 7
dEJd o o
yG c h. At least once per 10 ' years or after any modifications which could
-affect diesel generator interdependence by starting both diesel g 1j 2-
. generators simultaneously, during shutdown, and verifying that both w 706 1.r. yo g yf g diesel generators accelerate to at least 441 rpm in less than or equal to 11 seconds; and , 4
- l$ { { g gi. At least once per 10 years by:
- W j q t0 EJ 1) Draining each fuel oil storage tank, removing the accumulated 3ry3 o9t j, c L
, sediment and cleaning the tank using a sodium hypochlorite solution or its equivalent, and
1 2) Performing a pressure test of those portions of the diesel fuel
- 1 oil system designed to Section III, subsection ND of the ASME
@E )J, [S } .f Code at a test pressure equal to 110% of the system design f ressure.
Y N4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be dE9 3 reported in a Special Report to the Commission pursuant to Specification 6.9.2 g within 30 days. Reports of diesel generator failures shall include the informa-a tion recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revi-sion 1, August 1977. If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be C supplemented to include the additional information recommended in Regulatory-Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.
4.8.1.1.4 Diesel Generator Batteries - Each diesel generator 125-volt battery bank and charger shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying that:
- 1) The electrolyte level of each battery is at or above the low mark and at or below the high mark,
- 2) The overall battery voltage is greater than or equal to 125 volts on float charge, and
- 3) The individual cell voltage is greater than or equ.a1 to 1.36 volts on float charge.*
- b. At least once per 92 days and within 7 days after a battery discharge with battery terminal voltage below 110 volts, or battery
- overcharge with battery terminal voltage above 150 volts, by L verifying that
- 1) There is no visible corrosion at either terminals or
{ connectors, and lC l *Two different cells shall be tested each month, i
l l CATAWBA - UNIT 1 3/4 8-7 l
,,.,e- -- , - , , <
$',q ~
Y,~ '
, l 3s
- w ' '
'l
.~ '
~w
- DUKE POWER CoxPAmy '
r y , .
p.o. mox asses :
y~ c 7 :m ~
cuAararra, w.c. ses4e r . K l EAL B.TUGEER 1 tutzenown Y d # ""
November 21.-1984 i"
,Mr.LHarold R. Denton 1 Director
{ Office ~of~ Nuclear Reactor Regulation
'U. S. Nuclear Regulatory Commission
- . . . ' Washington, D._C. 20555: .
iAttention: Ms. E. G. Adensam,' Chief _
r
' Licensing Branch No.-4 Re:' Catawba Nuclear Station 1 Docket Nos. 50-413 and 50-414 J
Dear-Mr. Denton:
" 1 License Condition 20,-Internal Corrosion Protection for Fuel Oil Storage Tanks,s
~
'which islincluded in the preliminary draft of. Facility Operating License NPF-31
'for Catawba Unit 1, would require the' application of an internal corrosion 1 protection'to theLfuel oil storage tanks prior to startup following the first refueling outage or the submittal of justification for not coating = the tanks.
D
- Thelfollowing discussion summarizes Duke Power Company's position that an-internal-tank coating is not necessary. Also included
- is a response to
- Ms. Elinor G. Adensam's letter of November 7,1984.
D- System Description
~
_ cThe dieshi fuel oil system at Catawba includes four 45,000 gal, storage tanks 4;y;Eper unit or.:2= tanks per diesel. The tanks are fabricated from 3/8 inch nominal thickness carbon steel which includes a 1/32 inch corrosion allowance. Each
~
.. tank is approximately 12 feet in diameter and-buried under approximately 5 1='
feet of backfill:and a concrete pad. The Unit I fuel oil' tanks-were coated with motor oil following sand blasting and were filled with fuel oil in March 1980. _
A recirculation.and purification system takes suction from the flush mounted
- sample connection on-the bottom of the tank and discharges the fuel oil at a rate'of 25 gpm through a simplex filter (25 micron particle removal
- rating)'. The' supply lines to the day tank are connected by an outlet raised 6 inches above the bottom of the tank.
No' Regulatory' Basis for Internal Tank Coating As' discussed in Section 9.5.4.2 of the Catawba SER, the Staff concluded that
" Internal corrosion. protection for the fuel oil storage tanks, as required
- by_ Section 7.5 of ANSI Std N195, is not being provided". Section 7.5 of ANSI N195' states, " Protection against internal and external corrosion shall be provided.". On March 24, 1982 Washington Public Power Supply System requested an interpretation of this section by Mr. F. A. Dougherty, Chairman
~
y l
- e; 2;['; - , 1 y i#k S 3 MrhHar51d R. Dentin, Dir,tetor
- .
P : November 21; 1984 '
,[
- Page'Two- . . . .
f g, 8: -
m
- 'ANS 59.51. , f By an' unanimous vote of[ the connaittee, an internal corrosion tallowance was deemed to meet the requirements of Section.7.5. Therefore.
-ANSI N195:was not'an appropriate basis for requiring an. internal tank <
- cpating.-lIt'is our opinion that, contrary to Mr. Denton's April 28.-.1982 .
^ Office. Letter No. 2.-Revision ~2 that stated that'" Staff reviewers should not decrease nor:go beyond 'the scope and requirements of any specific SRP l section,: the Staff's requirement ' for an internal tank coating went beyond Kthe requirements'of the Standard Review Plan (NUREC-0800).
No Identified' Problem with Uncoated Tanks' The position'taken-by the Staff in the Catawba SER was based on an unsupported'
. . interpretation of. ANSI N195, not on plant. operating experience. 'At no time '
during the review. process has the-Staff identified any occurance of a problem-
- with. uncoated, buried fuel oil storage tanks.- On the contrary, internally icoated fuel oil tanks at the Hanford N-Reactor and'at Limerick (See-INPO SER
'2-84) have experienced problems with flaking and peeling of the coating.
~
.Therefore License. Condition 20 would not enhance plant safety but may instead
= degrade plant' safety.
LDuke has had over 40 years experience with uncoated, buried fuel oil tanks at (the Company'sLfossil and nuclear-stations. Our experience with these tanks is
~ testimony to the~ reliability of uncoated tanks. Inspections of buried tanks at the~ Lee,'Cliffside, Allen and Marshall Steam Stations have shown that-sinternal corrosion is,not a problem.with buried fuel oil tanks. The survey of
~
.m : local industries which was documented in'my letter of October 2,1984 further supports this conclusion.
Ju'stification for not Internally Coating' Catawba Tanks As a result of-the continuing controversy over License Condition 20,.a special inspection was performed on a 27,000 gallon underground fuel oil tank at Duke's
-Lee Steam Station. Details of this inspection were transmitted by my letter of 10ctober 2, 1984. After 34 years of service, minimal deterioration of the tank was noted. An ultrasonic inspection was made of the tank walls. Reductions in the mean tank wall thickness were noted at the top, bottom and sides of the tank Lof 0.0017, 0.0072, and 0.0002 inches, respectively. Based on the greater
- reduction noted in the bottom of.the tank, a 1/32 inch corrosion allowance would 4
be exceeded.infan additional 113 years of service at the present. corrosion rate.
.It should be noted that the Lee fuel oil tank did not have the benefit of design and operating features to minimize corrosion such as:
- 1) Cathodic protection
-2)- Fuel oil sampling to limit amount of water in new fuel -
- 3) : Tank maintained nearly full
_ 4) Periodic (10 year) tank cleaning
'The results of the Lee tank inspection provides reasonable assurance that the
< Catawba fuel oil tanks will perform their intended function without the application
.~of an internal coating. As noted in previous submittals, the Catawba fuel oil tanks
- have' additional design and operating features to further minimize tank corrosion:
7
~~ . 4 2.!'I
^ - Mr. Harold R4 Dentin, Dir:ctsr November. 21,41984'
, .Page Three f1) Cathodic protection (fully operable 6/85 for Unit 1)
-2) .'Use of high quality fuel
- 3) ; Tanks maintained nearly fulliin accordance with'the Technical Specifications.
- 4) Periodic'(Quarterly) drainage of accumulated water from the bottom of the tank
- 15) : Periodic (10 year) tank cleaning
-In order to provide further assurance that corrosion'of the buried fuel oil storage tanks at Catawba is not progressing at a faster. rate than expected, measurements of the tank wall thickness will be performed in conjunction with
-each 10 year cleaning. The measurement of the tank wall by ultrasonic ~or other means will include sufficient points to determine a statistical mean
~ thickness. . The resulting data will be evaluated and abnormal degradation (corrosion allowance exceeded) would be reported to the NRC pursuant to 10 CFR 50.73. LIn addition to the inspections during the 10 year cleaning. -
the Catawba Unit 2 tanks will be inspected prior to fuel load. . .
Conclusion Based on the above discussions, it is concluded that. License Condition 20 has been satisfied in that an internal tank coating-is not necessary and
.there'is reasonable assurance that the uncoated tanks will provide an adequatedieselgeneratorfueloilsupply.
Very-truly yours, fb.f.AA'- ll(/
Hal B. Tucker ROS: sib cc: .Mr. James P. O'Reilly, Regional Administrator
^
Mr. Jesse L. Riley U.LS. Nuclear Regulatory Commission Region II Carolina Enviromental Study Group 854 Henley Place 101 Marietta Street, NW, Suite 2900 Charlotte, North Carolina 28207
, Atlanta, Georgia 30323 Robert Guild, Esq. NRC Resident Inspector P. O. Box 12097 Charleston, South Carolina 29412 Catawba Nuclear Station '
Palmetto Alliance 2135 Devine' Street Columbia, South Carolina 29205
._,-,~,,c.__.-----. - - - - - * =" ' * * ' ' - - -