Proposed Tech Specs Re Reducing Turbine Valve Test Frequency by Allowing Frequency to Be Determined by Methodology in WCAP-11529, Probablistic Evaluation of Reduction in Turbine Valve Test FrequencyML20235V285 |
Person / Time |
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Site: |
Prairie Island ![Xcel Energy icon.png](/w/images/6/6c/Xcel_Energy_icon.png) |
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Issue date: |
09/28/1987 |
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From: |
NORTHERN STATES POWER CO. |
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To: |
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Shared Package |
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ML20235V263 |
List: |
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References |
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NUDOCS 8710150076 |
Download: ML20235V285 (5) |
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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube 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[Table view] |
Text
- . . .. .
EXHIBlT B i
2 License Amendment Request Dated September 28, 1987 l
Docket No. 50-263
-306 License No. DPR-42 l
-60 Exhibit B consists of marked up pages of the Prairie Island Technical Specifications showing the proposed changes listed below:
Page:
TS.4.1-2A l
fh0A50076 870928 p ADOCK 05000282 PDR
.. n.
3 Table TS.4.1-2A REV 75 6/26/85 9
'.,'. MINTMUM FREOUEUCIES FOR EOUIPMENT TESTS i FSAR Sect. ;
4 Test Frecuenev Reference l i
- 1. Control' Rod Assemblies Rod drop times All rods during each .7 of full length refueling shutdown or rods following each removal of the reactor vessel head; affected rods fellowing maintenance on or modification to the control rod drive system which could l affect performance of i those specific rods l
- 2. ~ Control Rod Assemblies .
' Partial move- Every 2 weeks 7 ment of all rods -
,. 3. Pressurizer Safety
Valves Inservice Testing Program 4; Main Steam Safety Set point Per ASME Code,Section II - i Valves Inservice Testing Program !
( '
- 5. Reactor Cavity Water level Prior to moving fuel -
assemblies or control rods and at least once every day while the I
-cavity is flooded.
- 6. Pressuri:er PORY Functional Quarterly -
Block Valves
- 7. Pressurizer PORVs Functional Every 18 months -
- 8. Deleted l
- 9. Primary System Leakage Evaluate Daily 4 l
'10. Deleted i
- 11. Turbine.stop valves, Functional dedch 10 )
governor valves, and ggt [ ( g) {
intercept valves.
(Part of turbine l overspeed protection.)
- 12. Deleted !
W !L. c _ : --" ie 1. .;
- J 22d ;f sole operac.wu. ..:n be r- ~ -- ---i;;.; a a leer th u 130 ppm y w. & - c;; a gy3 ;g ,, a 2
- _4 g _
eersor O s. lve s, s t un gsresp e v tve.s s.e s se b ye s .g st s..e n Q *n r p.s is.y v wes, s f *74 =8 k e k t. meekade/opy Press t<4 h 6.ic A P - //.ra.r " P,.,1, 1lg.* 8-
. Sq w.y consteen%4 ee refusa,, !
fos. t ~m.s to of "R eks trion k %cke 0 les Tese M.a for- rs.L s Q sn y an ney 'ereb e li/.'tf o ?.e k; -cLs, s e en-b lis W N R C. a.e c e p-tm e e e.r s'+
- r ts- s.~ar F ssile 0 G W K 2?Oi! M J)L !?6??'?] *V Y *" ' I* * * * ** * * ' k ** U L ** A U ' 'lL'L **' " h
E
, .i Tcblo TS.4.1-2A~
REV XX XX/XX/XX a
MINIMUM FREQUENCIES FOR EOUIPMENT TESTS FSAR Sect.
111g Freauency geference .,
J
- 1. Control Rod Assemblies Rod drop times All rods during each 7 of full length refueling shutdown or ]
rods following each removal J of the reactor vessel head; affected rods
-following maintenance on or modification to i the control rod drive j system which could I affect performance of I those specific rods
- 2. Control' Rod Assemblies Partial move- Every 2. weeks 7 ment of all rods
- 3. Pressurizer Safety Set point Per ASME Code,Section XI -
l Valves Inservice Testing Program
- 4. Main Steam Safety Set point Per ASME Code,Section XI - !
Valves Inservice Testing Program
- 5. Reactor Cavity Water Level Prior to moving fuel -
assemblies or control rods and at least once every day while the cavity is flooded _
r
. 6. Pressurizer PORV Functional Quarterly -
Bloch Valves
- 7. Pressurizer PORVs Functional Every 18 Months -
- 8. Deleted j
- 9. Primary System Leakage Evaluate Daily 4 j
- 10. Deleted
- 11. Turbine stop valves, Functional See (1) 10 governor valves, and intercept valves. l (Part of turbine overspeed protection)
- 12. Deleted (1) Turbine stop valves, governor valves and intercept valves are to be tested at a frequency consistent with the methodology presented in WCAP-11525 "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency", and in accordance with the established NRC acceptance criterig for the probability of a turbine missile ejection incident of 1.0x10' per year. In no case shall the turbine valve test interval exceed one year.
l
-_______-___-_---_-_-__-___-O
p.
EXHIBIT D License Amendment Request Dated September 28, 1987 Docket No. 50-263
-306 License No. DPR-42
-60 Exhibit D consists of WCAP 11529 "Probabilistic Evaluation of Reduction in Turoine Valve Test Frequency" (Non-proprietary version of WCAP-11525 "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency") .
e s t 4
?.
. ,. j EXHIBIT C' l
, l 6-
.. l v.
r-. License Amendment Request Dated September.28,~1987 i
Docket No. 50-263
-306- ,
License No. DPR-42
-60 Exhibit C consists of retyped pages of the Prairie Island Technical ,;
Specifications showing the proposed changes listed below: j ,
TS.4.1-2A i
e 9
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