|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively 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.... ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D7421988-07-11011 July 1988 Proposed Tech Specs Clarifying Method of Demonstating Operability of Source Range Monitor Channels ML20154M6321988-05-24024 May 1988 Proposed Tech Specs,Changing Alarm/Trip Setpoint and Measurement Range of Main Control Room Vent Radiation Monitors ML20154H1471988-05-19019 May 1988 Proposed Tech Spec Pages 3/4 5-6 & 3/4 5-8,providing Clarification to Eliminate Possibility of Misinterpretation ML20236C4661987-10-14014 October 1987 Proposed Tech Specs,Correcting Tupos & Tech Spec Internal Inconsistencies Re Radiological Environ Monitoring & Designation of Number of Valves in Table 3.6.3-1 ML20238C4471987-09-0404 September 1987 Proposed Tech Spec Pages 1-2,3/4 1-1,3/4 1-2,3/4 1-6, 3/4 3-4,3/4 9-3 & 3/4 9-7,changing Definition of & Footnotes Re Core Alteration ML20206F8791987-04-10010 April 1987 Proposed Amended Tech Specs Re Surveillance Testing for B-10 Enrichment Level of Standby Liquid Control Sys Tank ML20210C7791987-02-0404 February 1987 Proposed Tech Specs,Implementing Design Change That Will Equip Standby Liquid Control Sys W/Slightly More than Twice Equivalent Control Capacity Required by 10CFR50.62(c)(4) ML20212J4751987-01-21021 January 1987 Proposed Tech Specs,Incorporating License Change Application 6 to Implement Design Change to Lower Reactor Vessel Water Level of MSIVs & Steam Line Drain Valves from Level 2 to Level 1 ML20207P9631987-01-12012 January 1987 Proposed Tech Specs Re Location of Meteorological Towers & Composition of Independent Safety Engineering Group ML20206P2741986-06-26026 June 1986 Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept & Review of Operations Committee Responsibilities ML20140A8101986-01-20020 January 1986 Proposed Tech Spec Correcting Error in Basis for Location of Milk Control Sample & Eliminating Sampling Analysis If No Waste Batch Released During Month ML20137Z2941985-12-0909 December 1985 Revised Tech Spec Table 3.3.7.9-1, Fire Detection Instrumentation ML20136B4451985-11-16016 November 1985 Proposed Tech Specs Increasing & Relocating Fire Detectors & Modifying Reactor Coolant Leakage Detection Sys Surveillance Requirement ML20138C8791985-10-21021 October 1985 Proposed Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Nobel Gas Radiation Monitor ML20128M1371985-07-31031 July 1985 Technical Specifications for Shoreham Nuclear Power Station, Unit No. 1.Docket No. 50-322.(Long Island Lighting Company) SNRC-1181, Proposed Tech Spec 3.10.5 Suspending Provisions of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated for 120 EFPD1985-06-19019 June 1985 Proposed Tech Spec 3.10.5 Suspending Provisions of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated for 120 EFPD 1992-12-14
[Table view] 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] |
Text
_. - . . . - . - , - ----
~
?
1 l
REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE i
LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION-3.4.3.1 The following reactor coolant system leakage detection syste:ns shall be OPERABLE:
- a. The primary containment atmosphere particulate radioactivity i
monitoring system,
- b. The primary containment sump flow monitoring system, and
- c. Either the primary containment air coolers condensate flow indication system or the primary containment atmosphere gaseous radioactivity monitoring system. * -
APPLICA81LITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION: ,
With only two of the.above required leakage detection systems OPERABLE, r
(
operation may continue for up to 30 days provided grab samples of'the contain-ment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactive monitoring system is inoperable; otherwise, be in at.least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3.1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:
- a. Primary containment atmosphere particulate and gaseous monitoring systems performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months,
- b. Primary. containment sump flow monitoring system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL ALIBRATION TEST at least once per 18 months.,
- c. Primary containment air coolers condensate flow indication system perfomance of a CHANNEL FUNCTIONAL TEST
- at least once per 31 days and a CHANNEL CALIBRATION at.least once per 18 months.
I
- Notrequiredifcontainmentisclosed6dTnerte f
m'"28iM P
8ElIllia n.... ..... . . . . . . -.. - -
p -
' I!!STRil!U:NTATION
, FIRE DETECTION IIISTRUtn.;UTATION
,~ '
LIIIITII:G COUDITION FOR OMATION l' 3.3.7.9 As a minimum, the fire detection instrumentation for
! each fire detection zoac shoun in Table 3.3.7.9-1 shall be OPERABLE.
APPLICABILITY: Whenever equipment protected by the fire
] detection instrument is required to be OPERADLE.
].
ACTION:
i (a)
] With the number of OPERABLE fire detection instruments in one or more zones:
- I (1) Less than, but more than one-half of, the 1 Total Number of Instruments shown in Table
- 3.3.7.9-1 for Function A, restore the inoperable Function A instrument (s) to OPERABLE status within 14 days or within 1
?
hour establish a fire watch patrol to inspectthe cone (s) uith the inoperable instrument (s) at least once per hour, unless the_ instrument (s) is. located in an Q:ote 1D (inaccessiblezoneltheninspect inaccessible zonejat least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or that monitor the air temperature at least once per hour at the locations listed in specification 4.6.1.7 or Specification 4.7.9. '
(2) One less than the shown in Table 3.3.Total Number of Instruments 7.9.l_for Function B, or one-hal- or less of the Total Number of Instrumeats shown in Table 3.3.7.9-1 for
-- Function A, or with any two or more adjacent
- instruments inoperable,'within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect.
the zone (s) with the inoperabic instrument (s,
' ~ ~ ~
at least once per hour, unless the instrument (s) ~
is located in an Ghote fi cinaccessible __ zone,J then inspect thi .(inabeessible zone Et least once per 8 houl or monitor the air temperas tre ~
at least once .: hour at thq l_ocations lie 2d in Specificat ,n 4.6.1.7/3r'Socc1I1 cation'
.'T M (b) The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
% 1 1: {
(Nota A zone may bo declared to bo inaccessible during h
, specific operating conditions (e.g. containment i durin J unit operation, HPCI/RCIC d2 ring system testin g, main steam tunnel during unit operation) /
- - . - . . ~ . _.,....J s
W HLE 3.3.7.9 .1 -
FIRC DETECTION __gSTRUMElITATIOM SAPUTY-RELATED '0ME 4 TOTAL NUMBER OF IN'TRUMENTS* J
%I JiEAT SMOKE FLAME
~
j.; (x/p) (x/y) fx/y) 4-j, 1. _ Control Building i;
ii Emergency Switchgear-Room 101 0/6 6[0 Emergency Switchgear Room 102 0/6 60 f ,' -
Emergency Switchgear Room 103 cf Battery Room A 0/6 60
$j Battery Room B 0/2- (3
, 0 0/2 1
Battery Room C 0 / 3, (5j04[' 0 f Diesel Generator Room 101 0 /6' /r/c)
Diesel Generator Room 102 0/jil Sl Die'sel Genert. tor Room 103 0/9 {ylo(
.}
- i
._ Relay Room 0/24 @j0 OJ HVAC Equipment Room El. 44-0 3/0 d- HVAC E_quippent RooLEL._6J--0 _ 50 1
(CTiller Equip _ ment Room El. 44-03 10 Chiller Equipment Room El.-63~~0~ 9j/0 g
CRAC - FLT 2A El. 63-0 4/0
$ C $T ,2B,.El . 6,3 -0 j Corridor 4/0 p m 8 El. 25 a/0 t Corridor 9 E.l.-- 25 )
g 3/0
/
b 2. Reactor Building Prima _ryJontainment#
Secondary Containment El 8' 4/0 7 Secondary Containment El. 40' 30/0 Secondary Containment'El. 63' 37/o
. Secondary Containment. 14/0
+
~^
El.78'-7" .
4/0 42/0 95'-3 & 101'-6"
-El.ll2!-9" i
,~
~
- 2/0 55/0
- -Secondary Containment ~ ~
El 126'-9"~ 7 / O'
~ ~
Secondary Containment -
El 150'-9"& 159'-9" i. > 26/0 k h!JSocondaryContainmentEl175'-9" _
3/0-l MG Room 111 El 150'-9" T/0 MG Room 112 El 150'-9" 3 /0 MG Room 113A El 161'-0" 4 /0 MG Room 113D El 161-0" 3/0
.MCC West Room El 112'-9" 3/0 MCC East Room El 112'-9" 2/0 n ._ , _ , .c - ,
A --
TAllLE 3. 3. 7. 9-1 ( con t. i n ue d )
FIRH DMTECTIOU IHSTRUME!!TATIOli SAFETY-RELATED ZOME TOTAL UUMBER OF INSTRUMENTS
(x/y) (x/y) (x/y) f Remote Shutdown Panel Enclosure El 63'-0" HPCI Turbine El 8'-0" 0/2
'RCIC Turbine El 8'-0" 0/6 1TK607R Horisontal Cable Trays 2/0 1TX600R Vertical Cable Trays 5/0 RBSVS - FLT - 1A El 112'-9" 2/0 RBSVS - FLT - 13 El 112'-9" -
2/0 MCC Room El 40'-0" 2/0
^
-3. Turbine Building Electrical Manhole No. 1El 5'-8" 0/2 '
2/O (located in normal switchgear room)
- 4. Screenwell Pump Houase WfPump Cubicle A 0
mcPump Cubicle B 3/0
- 5. Yard Emergency Diesel F.O. Transfer Pump House A 2/0 Emergency Diesel F.O. Transfer Pump House B 2/0 Emergency Diesel F.O. Transfer Pump House C 2/0 TABLE NOTATIONS
x is number of Function A (carly warning arca fire detection '
and notification) instruments, y is number of Function B
~
~
.(actuation of fire supprcssion system and notification)
- ~
i~nstruments. _ _
~ ~
The fire di;oction instruments located within the primary containmer -ro not required to be OPERABLE during the performan a of Type A Containment Lea,kago Rate.Tosts. ;)
Heat detectors are non-restorabic spot'E p'e fixed temperature. ..
- Includes projected beam tyIe smoke detec.or i
8
- e -
* ~
- c. . i .
e gl SURVEILLAUCE REQUIREMENTS '
4 4
[
j.= 4.3.7.9.1 Each of the above required restorableLtype) fire y detection instruments which are acces~ 'UTe HEfing unit i operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire p' detectors which are not accessible due to specific unit operating conditions shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or when the specific detector becomes accessible, unless performed in the previous 6 months.
4.3.7.9.2 The supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.
4.3.7.9.2 "For nonrestorable spot-type detectors, after the7 fifteenth year at least two detectors out of every hundred, or fraction thereof, shall be removed every five years and j sent to a testing laboratory for tests. The detectors thet t
have been removed shall be replaced with new detectors. If a failure occurs on any of the detectors removed, additional detectors shall be removed and tested as a further check c4 the installation until there is proven to exist either a general problem involving faulty detectors or a localizen problem involving only one or two defective detectors".
/
~___
6 e-g o
-=
I b
k
% __ _m - ..,2 _ _1. , . _
_. . _ ,