|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20117L7271996-09-0505 September 1996 Proposed Tech Specs 4.2-2 Re Steam Generator non-repaired Tube Insp & 4.2-3 Re Steam Generator Repaired Tube Insp ML20092K8131995-09-19019 September 1995 Proposed Tech Specs,Providing Revs to Clarify Purposes to Maintain Accuracy of TS & Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20091P1041992-01-27027 January 1992 Proposed Tech Specs Re Steam Generator Tube Sleeving ML20205H3401987-01-12012 January 1987 Rev 3 to Reactor Test Program,Kewaunee Nuclear Power Plant ML20125B4491985-05-31031 May 1985 Plant,Cycle II Startup Rept,May 1985 ML20108F4791984-08-20020 August 1984 Suppl to Kewaunee Nuclear Power Plant 1984 Integrated Leak Rate Test Rept ML20092K4191984-06-30030 June 1984 Cycle 10 Startup Rept,June 1984 ML20080B9721984-01-12012 January 1984 Rev B to Emergency Plan Implementation Procedure EP-RET-3C, Post-Accident Operation of High Radiation Sample Room ML20080B9871984-01-12012 January 1984 Emergency Plan Implementing Procedure EP-TSC-7, Reactor Vessel Head Venting Time Calculation ML20083F7161983-10-27027 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-3 Re Unusual Event, EP-AD-4 Re Alert & EP-AD-5 Re Site Emergency ML20078L5791983-09-29029 September 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-3 Re Unusual Event, EP-AD-4 Re Alert & EP-AD-5 Re Site Emergency ML20078F4801983-08-16016 August 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-7 Re Notification of Unusual event,EP-AD-8 Re Notification of Alert & EP-AD-9 Re Notification of Site Emergency ML20077Q0481983-07-26026 July 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-ENV-8 Re Total Population Dose Estimate calculations,EP-RET-5 Re Plume Projection & EP-RET-6 Re Dose Projection ML20077B6001983-07-15015 July 1983 Cycle 9 Startup Rept for June 1983 ML20078G4201983-06-21021 June 1983 Rev D to Procedure EP-ENV-3F Manual Determination of X/Q (Green Bay Meteorological Data) ML20078G4331983-06-21021 June 1983 Rev D to Procedure EP-ENV-3G Manual Projection Calculation ML20078G4431983-06-21021 June 1983 Rev a to Procedure EP-RET-3D Containment Air Sampling Analysis Using Casp ML20078G4371983-06-21021 June 1983 Rev B to Procedure EP-ENV-3H Protective Action Recommendations ML20078G4061983-06-21021 June 1983 Rev E to Procedure EP-ENV-3E Manual Determination of X/Q (Knpp Meteorological Data) ML20078G3981983-06-21021 June 1983 Procedure EP-ENV-3D Primary Determination of Meteorological Data ML20078G3941983-06-21021 June 1983 Procedure EP-ENV-3C Primary Dose Projection Calculation - Ibm Personal Computer ML20078G3501983-06-21021 June 1983 Rev C to Procedure EP-AD-11 Emergency Radiation Controls ML20077E0041983-06-21021 June 1983 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-11 Re Emergency Radiation Controls & EP-ENV-3A Re Environ Protection Director Actions ML20078G3781983-06-21021 June 1983 Rev E to Procedure EP-ENV-3B EM Team Actions ML20078G3681983-06-21021 June 1983 Rev H to Procedure EP-ENV-3A Environ Protection Director Actions & Directives ML20069J5071983-03-10010 March 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-1 Re Plant Emergency organization,EP-AD-2 Re Emergency Class Determination & EP-AD-11 Re Emergency Radiation Controls ML20069F8351983-03-0101 March 1983 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedure EP-SEC-2, Security Force Response to Emergencies. Revised Table of Contents Encl ML20028D4811983-01-0303 January 1983 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-1, Plant Emergency Organization & EP-OP-3, Control Room Communications. Revised Index Encl ML20066E2691982-10-13013 October 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-2 Re Emergency Class determination,EP-AD-7 Re Notification of Unusual Event & EP-AD-8 Re Notification of Alert ML20062E0801982-07-0202 July 1982 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Revision E to Procedure EP-ENV-3A, Environ Protection Director Actions & Directives. Revised Index Encl ML20058F6741982-06-18018 June 1982 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-17 Re Communications & EP-RET-3C Re post-accident Operation of High Radiation Sample Room ML20054F3961982-05-21021 May 1982 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-ENV-3B Re Environ Monitoring Team Actions & EP-ENV-4A Re Sample Acquisition,Portable Instrument Use ML20052H8421982-04-16016 April 1982 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-7 Re Notification of Unusual Event & EP-AD-8 Re Notification of Alert ML20052B1051982-03-19019 March 1982 Public Version of Revision a to Emergency Plan Implementing Procedures EP-RET-2F, Personnel Decontamination. Revised Index Encl ML20042B2491982-02-18018 February 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure EP-EOF-1 Re Corporate Emergency Response Organization & EP-EOF-2 Re Emergency Operations Facility Activation.Revised Index Encl ML20049H4151982-01-29029 January 1982 Public Version or Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-1 Re Plant Emergency organization,EP-ENV-5C Sam II Operation & EP-EOF-4 Re Corporate Response to Alert.Revised Index Encl ML20040F9781982-01-15015 January 1982 Public Version of Revised Emergency Plan Implementing Procedures EP-OSF-1 Re Operational Support Facility Emergency Organization & EP-OSF-3 Re Work Requests During Emergency.Revised Table of Contents Encl ML20039H1491981-12-21021 December 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-1 Re Plant Emergency organization,EP-AD-3 Re Unusual Event & EP-AD-4 Re Notification of Unusual Event ML20038C3821981-10-21021 October 1981 Public Version of Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-1 Re Plant Emergency organization,EP-AD-2 Re Emergency Classification Determination & EP-AD-3 Re Unusual Event ML1116601091981-08-0707 August 1981 Proposed Amend 46 to Tech Specs 3.4,3.10,Table 3.1-2,Figures 3.1-1,3.1-2,3.10-7 & Pages 3.1-2,3.1.2a,3.1.2b,3.1-2,3.1-3, 3.1-6,3.1-7,4.2-2a,4.2-8 & 6-2 for Pressure Safety Isolation Valves & Normal Operation Heatup/Cooldown Limits ML20038A5641981-07-0101 July 1981 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures ECD 16.1 Re Corporate Emergency Response & ECD 16.2 Re Emergency Operations Facility Activation ML20038A5761981-06-0303 June 1981 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures ECD 16.1 Re Corporate Emergency Response & Acd 12.1 Re Emergency Organization Structure ML20038A5631981-03-31031 March 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Acd 12.1 Re Emergency Organizational Structure,Acd 12.3 Re Unusual Event Notification & Acd 12.4 Re Alert ML20038A5661981-02-27027 February 1981 Public Version of Radiological Emergency Response Plan Implementing Procedures,Description of Meteorological Monitoring Sys Implementation & Public Info Plan ML19210C9981979-11-16016 November 1979 Proposed Amend 41 to Tech Specs,Changing Limit for Reactivity Anomalies for Comparison of Measured to Predicted Boron Concentrations to 1% Reactivity ML19256E0081979-10-19019 October 1979 Proposed Tech Spec Amend 40,adding Fire Protection Sys Committed to in Amend 23,deleting Mods Required as License Condition,Adding 5-man Fire Response Requirements & Correcting Inconsistencies 1996-09-05
[Table view] Category:TEST REPORT
MONTHYEARML20125B4491985-05-31031 May 1985 Plant,Cycle II Startup Rept,May 1985 ML20108F4791984-08-20020 August 1984 Suppl to Kewaunee Nuclear Power Plant 1984 Integrated Leak Rate Test Rept ML20092K4191984-06-30030 June 1984 Cycle 10 Startup Rept,June 1984 ML20077B6001983-07-15015 July 1983 Cycle 9 Startup Rept for June 1983 1985-05-31
[Table view] |
Text
- .. . .. - . _ .
u .
- N1-67.lA L,
,/
January 22, 1985
, . Attachment to Letter from D. C. Hintz to W. S. Little t
Supplement to -
Kewaunee's 1984 ILRT Report
, Originally Submitted August 20, 1984 i
i 1
a 4
' (
f 4
4 i
Y Y l
l l
t B503120449 850122 PDR ADOCK 05000305 G PDR; 6
7
s
..
- Mr. W. S. Little January 22, 1985
~Page 1 Introduction This report presents the 'as-found' containment leakage rate calculation for the
" " ~ '
"Kewaunee Nuclear Plant Containment at the end of Cycle IX. Type C leakage, greater than the capacity of the local leak rate tester, was identified through a containment penetration with redundant isolation valves in series. The 'as-found' integrated leakage rate is determined by combining the directly measured containment leakage with a conservative measure of (pre-post) repair differen-4 tial leakage. The combination of the directly measured 1984 integrated leakage rate and the (pre-post) repair differential leakage could not be quantified.
This is considered a failure of the 1984 Type A test.
As stated in 10 CFR 50, Appendix J, V.B.3, upon failure of a Type A test the following points shall be covered in a summary report:
An analysis and interpretation of the test data The least squares fit analysis of the test data The instrumentation error analysis The structural conditions of the containment or components, if any, which contributed to the failure in meeting the acceptance criteria Results and analyses of the supplemental verification test employed to demonstrate the validity of the leakage rate test measurements shall also be included.
Section I of this report contains the 'as-found' leakage rate calculation and sections II through VI discuss the five (5) points required by 10 CFR 50,
~
Appendix J, V.B.3.
l l
l
.a . _ - - _ _ _ .
.. "Mr. W.' S.. Little-
. January 22, 1985 Page 2 I. 'As Found' Containment Leak Rate Type B and C leakage tests were performed during the 1984 Refueling-Outage prior to the Type A test. This order of testing is consistent with KNPP Technical Specifications and exemptions granted to WPSC from Appendix J provided a conser-vative measure of (pre-post) repair differential leakage is added to the Type A i results.
- When Type C leakage repairs are made prior to and during the same outage as a Type A test, (pre-post) repair differential leakage added to the Type A test will include improvements in the penetration's overall ability to isolate con-tainment; e.g.,
(1) Penetration with 2 testable isolation valves in series:
Before repair: Valve 1 leaks 8 SCFH Valve 2 leaks 6 SCFH
- After repair
- Valve 1 leaks 2 SCFH Valve 2 leaks 1 SCFH i ' Repaired leakage': 5 SCFH (2) Penetration with 2 testable isolation valves in series:
Before repair: Valve 1 leaks 8 SCFH Valve 2 leaks 6 SCFH After repair: Valve 1 leaks 2 SCFH i
Valve 2 leaks 5 SCFH
' Repaired leakage': 4 SCFH i
IMrc W.~ S.' Little
' January 22, 1985 Page 3 ' l Penetration geometries other than those with 2 testable isolation valves in
., , series will be evaluated on a case-by-case basis using appropriate conser- ;
vatisms. -Type B leakage repaired prior to and during the same outage as a Type A test will also be evaluated on a case-by-case basis using appropriate conser-l vatisms. - -
1984 i
As-Found Integrated Leakage Rate Determination Kewaunee Nuclear Power Plant Table 1 Leakage Repaired in 1984 Prior to the Type A Test Penetration- Initial Final Repaired Repaired Leakage Leakage Leakage i- 12 0.088SCFH 0.053SCFH 0.035SCFH/1.54 x 10-5 wt.%/ day 111 >20SCFH 0.068SCFH >20SCFH/>8.77 x 10-3 wt.%/ day
.I
!AsFound = Leakage Rate + Type B&C Leakage Repaired i Integrated Determined ~ Prior to Type A Test Leakage Rate With Type A Test As Found Integrated = 0.0162 wt%/ day + 1.54 x 10-5 wt%/ day + >8.77 x 10-3 wt%/ day l Leakage Rate
= >0.0250 wt%/ day-
- . Note'that the 'as-found' leakage rate is indeterminate. This resulted from the
, leakage through redundant isolation valves at penetration #11 exceeding the
! capability of the measuring device.
l
!' I See LER 305-84-006~
i
Mr. W. S. Little !
January 22, 1985 ,
Page 4 '
I
-Since the 'as-found' 1984 Type A test results are not quantified it cannot be positively'said that the test passed, nor can it be positively concluded that the test was a failure. Conservatively, the 'as-found' 1984 Type A test is con-sidered a failure.
II. Analysis and Interpretation of the Test Data The 1984 ILRT test data were analyzed using the Mass Point Method (ANSI 56.8-1981). A summary of the data reduction method can be found in Appendix B of Kewaunee's 1984 ILRT Report (reference 1). The raw data and i
intermediate calculation results are in Appendix D of the same report.
The calculated leakage rate, 0.0162 wt%/ day (at 95% UCL), demonstrates the leak tightness of Kewaunee's Containment for Cycle X.
III. Least Squares Fit Analysis of the Test Data A least squares analysis was performed with the following as the independent and dependent variables, respectively:
[ Change in time Weight fraction of containment \
-measured from t=0 atmosphere remaining up to and
( , including data set i )
The s' ope of the curve is the containment leakage rate in weight fraction per hour and the y intercept is the weight fraction in containment at time zero.
This calculation was performed via computer; the data and results are found in the 1984 Kewaunee ILRT report, Appendix D.
-_-__ __ 9
l Mr. W. S. Little January 22, 1985 Page 5 IV. Instrumentation Error Analysis _
A figure of_ merit analysis for the instruments used in the 1984 ILRT is pre-sented in Appendix B of the 1984 Kewaunee ILRT report (reference 1).- The analy-sis is consistent with ANSI 56.8-1981, Appendix G. The instruments were
, determined to be suitable for their intended use.
V. Conditions Which Contributed to Failure of the Type A Test Kewaunee's 1984 'as-found' Type A test was considered a failure since Type C j leakage greater than the capacity of the local leak rate tester was identified prior to the Type A test through redundant isolation valves.1
^
LP-M4
\/ -
\/
A '
O nuoE onace LD Mt Containment The leakage was repaired by replacing the seat ring gaskets in valves LD-4A and LD-4B and adjusting the stroke on LD-6. Note that LD-4A is in parallel with LD-4B which together are in series with LD-6. These repairs resulted in reducing the Type C leakage through penetration #11 from >20SCFH to 0.068 SCFH.
VI. Results and Analyses of Supplemental Verification Test Employed to Demonstrate the Validity of the Leakage Rate Test Measurement The condition which caused the Type A test failure was corrected prior to per-formance of the Type A tests, i.e., B and C tests were performed prior to the A I See LER 305-84-006
~
. - . - - - o
1 Mr. W. S. Little January 22, 1985
- Page 6 i
~ !
test. Therefore, the relevant supplemental test is the same supplemental veri-fication test that illustrated acceptable results of Kewaunee's 1984 Type A 7
test. The supplemental test was successful and is described in section I.1 of Kewaunee's 1984 Type A test report (reference 1).
l
.