Proposed Tech Specs,Changing Requirements So Testing of Turbine Generator Control Valves Need Only Be Conducted on Monthly BasisML20116J009 |
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Catawba |
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Issue date: |
04/29/1985 |
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From: |
DUKE POWER CO. |
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Shared Package |
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ML20116H995 |
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References |
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NUDOCS 8505020425 |
Download: ML20116J009 (3) |
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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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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
INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed P'rotection System shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
- a. With one stop valve or one control valve per high pressure turbine steam line inoperable and/or with one intermediate stop valve or one intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turoine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:
a.
At least once per 7 days while in MODE I and while in MODE 2 with the turbine operating, by cycling each of the following valves through at least one complete cycle fram the running position:
- 1) Four high pressure turbine step valves, mu
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7 _m Z/) Six low pressure turbine intermediate stop valves, and 3/) Six low pressure turbine intercept valves.
- b. At least once per 31 days while in MODE 1 and while in MODE 2 with the turbine operating, by direct observation of the movement of each of the above valvesgthrough one complete cycle from the running position, ggg g Q.y g4/ g/q
- c. At least once per 18 months by performance of a CHANNEL CALIBRATION on the Turbine Overspeed Protection Systems, and
- d. At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.
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GENERAL ELECTRIC COMPANY SCHENECTADY, NEW YORK Technical Information Letter No. 969 MAY 22, 1984 Periodic Turbine Steam Valve Test - Nuclear Units s
CE recommendations for periodic nuclear turbine steam valve tests as contained in the Turbine Instruction Book call for daily test of the main stop, inter-mediate stop, and intercept valves and weekly test of the control valves.
These recommendations are similar to the test frequencies that have been in practice since the late 40's and early 50's on fossil-fueled turbines.
The operating experience accumulated on in-service nuclear units during the past 24 years has shown considerably lower valve failure rates than those values upon which the recommendations were based. These reduced failure rates are due to many design improvements to the nuclear turbine valves and controls that have been incorporated through Technical Infonnation Letters (TIL's) and Engineering Change Notices (ECN's).
'In the " Memo Report - Hypothetical Turbine Missiles - Probability of Occur-rence," dated March 14, 1973, the probability of runaway failure and wheel burst of a GE nuclear' turbine was given, based on the nuclear experience up to that time. Included in the probability calculations were the recommended valve test intervals; i.e., daily f or main stop and intemediate stop & inter-cept valves, weekly for control valves. The Nuclear Wheel Information Letter No. 2, dated November 8, 1982, gave comparative values for the increased over-i speed probabilities due to increasing test intervals.
Based on past in-service experience with nuclear turbine steam valves, turbine steam inlet valve reliability and testing intervals are no longer the major contributing factors in determining hypothetical turbine missiles. The over-all probability of a hypothetical missile is therefore increased only a negligible amaunt by increasing the test interval of the valves. Increasing test intervals will correspondingly decrease the probability of a system upset during such testing and should therefore increase the nuclear plant avail.
ability. Of course any problems detected during any testing should be brought
! to the attention of your local A&ES service engineer. The service engineer may call on the LST-G Dept. if further assistance is necessary.
i COPYRIGHT GE!JERAL ELECTRIC COMPAL"t, 1984
- The enforar..us
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cer ra.e.cs Mc.ever, .inte the ogwr.uee c' ? our pl.mt antolwee us.ny f.caore not .tuun s,vr kno...c ge nc ..nce ope r.uon of the pt.nt i. enuus your centreil anc ulum.Le
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,2 .r. :. 2 c r--: i or..m ..u c o .n-< ,.: ui.i m.3 e. cier.c w, h.. e i-e n a nc o ree s .. . e..e e: ., , . r.r e .. .r.r er a..uon ce r.-e ... os . neu ee n .. c a.imm u..i oener e ,
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Effective with this Technical Information Letter, the recommended valve test intervals for nuclear turbines are:
Main Stop Valves Weekly Intermediate Stop Valves Weekly Intercept Valves Weekly Control Valves Monthly Recommended test intervals for other control components remain unchanged.
Utilities should . revise their Instruction Books to the new test intervals based on this TIL. Revised Instruction Book Articles will not be sent from General Electric Co.
Because of the higher temperature and resulting increased oxidation build-up on the stems and bushings of fossil-fueled turbines, the valve test interval
-recommendations remain unchanged; i.e., daily test of the main stop, combined intercept and reheat stop valves, and weekly test of the control valves.
If your Te'chnical Specification or other documentation upon which your NRC operating license is based contains any obligation or commitment to test on a specific schedule, it is suggested that you take appropriate steps to modify that document if you wish to change your test intervals to these new recommendations.
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