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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994
Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny
ML20071Q2491994-07-31031 July 1994
Rev 3 to Shoreham Decommissioning Project Termination Survey Plan
ML20063D0261993-12-31031 December 1993
Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan
ML20059K1061993-08-25025 August 1993
Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny
ML20073E9171993-07-0707 July 1993
Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa
ML20063D0121993-04-30030 April 1993
Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan
ML20128P6781993-02-17017 February 1993
Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation
ML20128P6981993-02-0909 February 1993
Rev 1 to 67X001.10, Termination Survey Design
ML20128P6571993-02-0202 February 1993
Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure
ML20128P6661993-01-29029 January 1993
Rev 0 to 67X001.03, Termination Survey Quality Control
ML20128P7011993-01-19019 January 1993
Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations
ML20128P6941993-01-0808 January 1993
Rev 1 to 67X001.09, Termination Survey Background Assessment
ML20128P6831993-01-0808 January 1993
Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt
ML20128P6751993-01-0707 January 1993
Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt
ML20128P6701993-01-0606 January 1993
Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure
ML20127B8101993-01-0505 January 1993
Plan for Phased Decommissioning of Liquid Radwaste Sys
ML20125D5071992-12-14014 December 1992
Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements
ML20128P6881992-12-10010 December 1992
Rev 0 to 67X001.08, Survey Unit Classification Description
ML20128P7211992-10-31031 October 1992
Rev 0 to Shoreham Decommissioning Project Termination Survey Plan
ML20128P7151992-10-22022 October 1992
Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description
ML20128P6471992-10-0101 October 1992
Rev 0 to 67X001.01, Termination Survey History File Content & Preparation
ML20094M7681992-03-27027 March 1992
Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992
ML20086K0981991-12-0505 December 1991
Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel
ML20079N0681991-11-11011 November 1991
Excerpts from Shoreham Solid Waste Process Control Program
ML20079P3981991-10-31031 October 1991
Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively
ML20090A8321991-08-0707 August 1991
Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm
ML20082K9491991-05-31031 May 1991
Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual
ML20070H6191991-03-11011 March 1991
Proposed Tech Specs Removing License Condition 14 from License NPF-82
ML20070D4921991-02-26026 February 1991
Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls
ML20058E3051990-10-30030 October 1990
Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs
ML20059G3701990-08-30030 August 1990
Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation
ML20056B5081990-08-21021 August 1990
Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls
ML20058N5431990-08-10010 August 1990
Proposed Tech Specs Re Defueled SAR
ML20044A8011990-06-28028 June 1990
Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status
ML20006F4711990-02-20020 February 1990
Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural....
ML20006F4881990-02-20020 February 1990
Draft Odcm.
ML20064A3381990-01-31031 January 1990
Rev 15 to 4170002, Odcm
ML20005F2481990-01-0505 January 1990
Proposed Tech Specs Re Defueled Facility OL
SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989
Suppl 15 to Startup Rept for Period 890501-0801
ML20246N9731989-07-13013 July 1989
Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process
SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989
Suppl 14 to Startup Rept for Period 890201-0501
ML20246E5891989-04-30030 April 1989
Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company)
ML20246N4871989-01-31031 January 1989
Rev 14 to Offsite Dose Calculation Manual
SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988
Suppl 12 to Startup Rept for Period Aug-Nov 1988
SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988
Proposed Tech Spec Table 1.2, Operational Conditions
ML20235U9341988-09-13013 September 1988
Rev 5 to Solid Waste Process Control Program
SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988
Suppl 11 to Startup Rept for May-Aug 1988
ML20151D7141988-07-15015 July 1988
Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators
ML20151D6081988-07-13013 July 1988
Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures
ML20151D4191988-07-13013 July 1988
Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution
1994-07-31
[Table view]
Category:TEST REPORT
MONTHYEARSNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989
Suppl 15 to Startup Rept for Period 890501-0801
SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989
Suppl 14 to Startup Rept for Period 890201-0501
SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988
Suppl 12 to Startup Rept for Period Aug-Nov 1988
SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988
Suppl 11 to Startup Rept for May-Aug 1988
SNRC-1458, Suppl 10 to Startup Rept for Period 880201-0501,Shoreham Nuclear Power Station1988-05-11011 May 1988
Suppl 10 to Startup Rept for Period 880201-0501,Shoreham Nuclear Power Station
ML20236Q0741987-11-11011 November 1987
Suppl 8 to Startup Rept for Period 870801-1101
SNRC-1357, Suppl 7 to Startup Rept for 870501-08011987-08-11011 August 1987
Suppl 7 to Startup Rept for 870501-0801
SNRC-1336, Suppl 6 to Shoreham Nuclear Power Station Startup Rept for Feb-May 19871987-05-14014 May 1987
Suppl 6 to Shoreham Nuclear Power Station Startup Rept for Feb-May 1987
ML20211C2451987-02-0606 February 1987
Suppl 5 to Startup Rept for 861115-870201
ML20212Q9501987-01-31031 January 1987
Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C Periodic Test
ML20198A0011986-05-15015 May 1986
Suppl 2 to Startup Rept for 860215-0515
SNRC-1234, Suppl 1 to Startup Rept for 851115-8602151986-02-14014 February 1986
Suppl 1 to Startup Rept for 851115-860215
ML20137B4871985-11-15015 November 1985
Shoreham Nuclear Power Station Startup Test Rept
ML20112J7191985-02-0404 February 1985
Rev a to Qualification Rept for Model KDI-1000 High-Range Containment Area Radiation Detector & Mineral-Insulated Cable Sys
ML20100G3991984-12-0303 December 1984
Tdi Emergency Diesel Generator 103 10 Cycle Confirmatory Test/Insp Rept
ML20083G3151983-11-22022 November 1983
Shoreham Diesel Generator Recovery Program
ML20079J6981983-10-31031 October 1983
Field Test of Emergency Diesel Generator 101
ML20072P0541983-07-12012 July 1983
Test Review,Data Analysis & Review of Emergency Diesel Generator Operational/Reliability Problems at Shoreham,Unit 1, Final Rept
ML20072B1471983-02-0808 February 1983
Seismic Qualification Reevaluation,Class IE Equipment, Differential Pressure Transmitter for Shoreham Nuclear Power Station,Unit 1
ML20069D9611982-12-31031 December 1982
Reactor Containment Bldg Integrated Leak Rate Test Type A,B & C Preoperational Test
ML20195C6321982-12-22022 December 1982
Structural Response of Containment Structure,Shoreham Nuclear Power Station - Unit 1 During Structural Acceptance Test
ML20072B1511982-11-22022 November 1982
Rev 23 to Dynamic Qualification,Recirculation Discharge Gate Valve for Shoreham Nuclear Power Station,Unit 1
ML20066B5001982-09-30030 September 1982
Independent Verification,Shoreham Nuclear Power Station, Vol I,Executive Summary.Final Rept
ML20072B1371981-04-0303 April 1981
Rev 2 to Seismic Qualification Reevaluation,Class IE Equipment for Shoreham Nuclear Power Station,Unit 1
ML19340E1381980-12-22022 December 1980
Preliminary Version of Reactor Bldg Separation Analysis Rept.
ML20195C6111978-10-11011 October 1978
Addendum 1 & Spec for Structural Acceptance Test. Copyrighted Matl
ML20067D9441977-01-20020 January 1977
to 200 Series Low Voltage Electric Penetration Qualification Test Rept
1989-08-15
[Table view] |
Text
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- SHOREHAM NUCLEAR l. l POW
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SEISMIC QUALIFICATION REEVALUATION 1
CLASS lE EQUIPMENT
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' LOCAL PANELS i Rev.2 ;-
SAI # 029-QA-80-PA ",
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' Prepared by: E. S , RAMADASo , ~~kQ / y ;
.6, Date: April 3,1981 l
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Table 2 SHOREHAM NUCLEAR POWER STATION
- 555 CLASS 1E LOCAL PANEL DEVICES WITH. SINGLE AXIS MALFUNCTION LIM gx! MUM EXPECTED ACCELERATION AT MOUNTING. LOCATION.
I IEEE 344-71 CAPABILITY MAX. EXPECTED ACC. AT ANY GE PPD DWGf (MAX.ACCN ON TESTED PANELS) LOCATION ON MPL i SHOREHAM PANELS g 3,3 y fh s.s y 3
.' ! I 831.NolB. Ell-N021.E21-N06, 145C3003 15.0 l, 15.0 . '; 15.0 3.0 '
e 5.4 8 s
1.41 E41.N06 E51-N02
' e 821.N06 N09.N021;B31.N019- '
n022 ;E 21-N04.N05: E41-401, 145C3009 11.0 '
11.0 11.0 3.0 '
8 6.8 l1.41 N04.N 05:E 51 -N 018,N 017 ,
I s s s 1.41
[41-N010 E51-N06,N08 N019 145C3011 15.0 , 15.0 s 15.0 3.0 8 6.8 C71-h02. Ell-N010.N0ll; ! ! f f E41-N012.N021;E51-N09, 145C3046 13 l 13 8 10 3.0 - 5.4 8 1.41 u012,NO30 , !
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5 g W c71-N04 158C7055' 5 l. 10 l 10 3.0 l 4.5 s ,
1.41 i l i ;
821-N037 159C4383 10 l 10 I, 10 3.0 l 5.4 l1.41 I !- I !
B21-N024.h026.NO31.N042 159C4384 10.0 l 10.0 r.
10.0 3.0 s 4.5 j 1.41 i
- i 821-N025 159C4445 15.6 !. 5.0 l .
10 3.0 l 4.5 f1.41 i i*
29.0 l 29.0 29.0 3.0 1.41 j E21 N07 N 159C4606 f5.4 i I 621-R04; Ell 802.R03- e e 1.41 E21.R01.E41-R01.R03-R05; N 163C1184 15.0 15.0 15.0 3.0 l 5.4 ;
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E11-N022,E51-NO31 % 163C1185 15.0 l 15.0 l 15.0 3.0 l 4.5 l 1.41 I ! ! !
C32-N05.N03: Ell-N026 3 3 e i e N028;E21-N01;E41-N09.N013. \ 16 C1186 10 i 10
. e 1016.N019:E51 N04.N05 l 821-N055 163C1292 5.5 5.5 3.7 3.0 l4.5 ! 1.41 4 I I ! l
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NO39.N045;B31-N018.E41 N 164C5359 15.0 s* 15.0 : 15.0 3.0 ; 5.4 8 1.41 s
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"* O b.YALINCIA Oftlyt. FULLERTON. CAL'FORNIA 33g3 g TELEPHONE &s 734/t79.g33o
' 24 September 1973 ,
FUiLERTON DIVISIO!! REPORT NUMBER F-73493
. Darksdale~P. O. Number 31600 .
A. TEST: Seismic Vibration
D. RESULTS:_
This is to certify that the test item was subjected
- to the Seismic Vibration Test according to the specifications.
The test are detailed on the second page.
( OGDEN TECIINOLOGY LABORATORIES, INC. . .
0I R. D. Short, Division Manager cvl '
.J P G T. P. Smith, Project Engineer Subscribe. and sworn to before me this 24th day of September 1973. ,
e i e_OFFICIAL SEAL e <
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pC-AMADOR HERNANDEZ P&OTAFtY FV1'O + CAUFORNW 5
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. ?*. Q ! UNotarydeblic <?_ r & l r -in k.,d b " M'"L f an)d for the County of Orange, State Amador
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of California. My commi 'n expires April 8, 1977. ,- , .
<'e N r Nd I ((pf,. . .
- *Rf J. McKellig6tt, <- ,
. Quality' Assurance Manager i ,
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Details of Seismic Vibration Test
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- 1. Resonance Search A. Procedure , .
Frequency Range : 2 to 33 Hz -
Vibration. Levels : - 0.2g'from 2 to 5 Hz +
A*0.5g from 5 to 33 Hz -
Sweep Rate : .
0.8' octave / minute Duration of Test : 9 minutes .
Applied Pressure.: 85 ps'ig '
Chatter Monitor : 10 Microseconds Recording : Response accelerometer mounted on the test item in the axis of vibration.
B. Nesults .
There were no indication of resonant frequencies.
- 2. Dwell Oibration ,
A. Procedure '
e( -
Frequency r,
Ulth.mateLevel* Duration (Seconds)
- 2. H z 1 inch da 5 Hz 30 10 Hz 1 inch da 30 24g
30 179 30 3
20 Hz *179 25 Hz 30 j 124g 30 Ur, 30 t ~ 1299 30
' *faiinre Level. gradually mode, chatter. increased at each frequency in attempt to induco Applied Pressure : 85 psig
'( Chatter Monitor .
10 microseconds -
B.
i ,.
Results " -
- j -
There was no indication of contact chatter in excess of 10 l microseconds
.A above.
up to and including the ultimate levels shown'in Thesefrequencies.ultinate levels are vibration machine limits i
,\.
.at the different '
' There fro = the. wastests. no visib1e evidence of physical damage rest.1 ting
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SAllPLE CALCULATION
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PRESSURE SWITCH NATURAL FREQUENCY Item: Barksdale Pressure Switch Model !!o PlH-M340SS-V MPL tio. E21-t:008/f;039 PPD flo.159C4602P002 Hechancial Construction:
- Sensi ng el ement ------------------ diaphragm sealed piston Diaphragm material---------------- Viton Diaphra gm diameter---------------- 1.625" Pi ston trav el -------------------- 0.040" max Spring constant ------------------ 100 lb/in Mass of mechanism ---------------- 0.1 lb Natural Frequency: .
f " - where k = spring constant l n 2 m = . mass of mechanism l
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=
k# _ . _b _ .
_g.. ., _ y,, 3, i
= 99hz L -
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