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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution B14554, Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation1993-08-0909 August 1993 Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20046A4651993-07-21021 July 1993 Proposed Tech Specs Re Radioactive Liquid Effluent Monitoring Instrumentation ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20045D8531993-06-22022 June 1993 Proposed TS Changes to Include Augmented Erosion/Corrosion Program for Piping in AFW Bldg & Related Piping B14450, Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences1993-05-31031 May 1993 Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences ML20036B9811993-05-28028 May 1993 Proposed Tech Specs SR 4.6.1.2,citing 10CFR50,App J,Which Incorporates Total Time Method & Mass Point Method for Calculating Containment Integrated Leakage Rates B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-061993-05-19019 May 1993 Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06 ML20044E4131993-05-17017 May 1993 Proposed Tech Specs Re Fire Protection B14461, Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop1993-05-0404 May 1993 Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop ML20036A1891993-04-30030 April 1993 Proposed TS 3/4.8, Electrical Power Sys, Paragraph 4.8.1.1.2.b,that Deals W/Automatic Load Sequence Timers on EDGs to Be Implemented During Upcoming Cycle 17 Refueling Outage ML20035G8601993-04-23023 April 1993 Proposed TS Shutdown Margin Requirements for Change in Cladding from Stainless Steel Clad Core to Zircaloy Cladding for Cycle 18 Operation ML20035A7561993-03-22022 March 1993 Proposed Tech Specs Addressing Special Test Exceptions, Electrical Power Sys Shutdown Relief Valves & Service Water Sys ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup B14391, Proposed TS 4.6.1.2 Re Calculating Containment Integrated Leakage Rates During Surveillance Testing1993-03-16016 March 1993 Proposed TS 4.6.1.2 Re Calculating Containment Integrated Leakage Rates During Surveillance Testing ML20128E6811993-01-29029 January 1993 Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases ML20128E5501993-01-29029 January 1993 Proposed Tech Specs Re Steam Generator Repair Criteria B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria B13751, Proposed Tech Specs Re Steam Generator Overfill Protection1991-02-28028 February 1991 Proposed Tech Specs Re Steam Generator Overfill Protection ML20029B0671991-02-28028 February 1991 Proposed Tech Specs Adding Footnote to Tech Spec Table 4.3.1 Item 16, Reactor Trip Sys Breakers ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20059F0011990-08-25025 August 1990 Proposed Tech Specs Re ESFAS Instrumentation B13597, Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability1990-07-26026 July 1990 Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability B13570, Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases1990-07-0505 July 1990 Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases B13555, Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation1990-06-25025 June 1990 Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation ML20043G6311990-06-14014 June 1990 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements ML20043H0231990-06-0808 June 1990 Proposed Tech Specs Re Reactor Trip Sys Instrumentation Response Times B13520, Proposed Tech Specs Supporting Cycle 16 Operation1990-05-0909 May 1990 Proposed Tech Specs Supporting Cycle 16 Operation B13503, Proposed Tech Specs Re Fire Detection Sys,Spray &/Or Sprinkler Sys & CO2 Sys1990-04-24024 April 1990 Proposed Tech Specs Re Fire Detection Sys,Spray &/Or Sprinkler Sys & CO2 Sys ML20033F5551990-03-14014 March 1990 Proposed Tech Specs,Allowing Testing of Individual Rod Position Indication Sys During Power Operation B13450, Proposed Tech Specs,Relocating Table 4.4-5, Reactor Vessel Matl Surveillance Program-Withdrawal Schedule & Changing Figures 3.4-3,4 & 5 Re Thermal Shields1990-02-16016 February 1990 Proposed Tech Specs,Relocating Table 4.4-5, Reactor Vessel Matl Surveillance Program-Withdrawal Schedule & Changing Figures 3.4-3,4 & 5 Re Thermal Shields ML19332E4381989-11-22022 November 1989 Proposed Tech Specs Re Reactor Trip Sys Trip Setpoints & ESFAS Instrumentation B13380, Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal1989-09-29029 September 1989 Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal 1999-08-24
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20212A6681997-09-29029 September 1997 Final Rept Unrestricted Release Confirmatory Survey Program ML20206D1071997-06-30030 June 1997 Rev 10 to ODCM for Hnp ML20206D1031997-05-31031 May 1997 Rev 10 to Radioactive Effluent Monitoring Manual ML20148G9191997-05-30030 May 1997 Rev 0 to Cyap Haddam Neck Plant Radiation Protection Improvement Plan ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification Training Program Implementing Procedure ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification Training Program Implementing Procedure ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20216B3071997-02-28028 February 1997 Rev 8 to ODCM for Haddam Neck Plant ML20249B7761997-02-19019 February 1997 Rev 4 to Hwm 15.1-7, Spill Prevention Control & Countermeasure Plan ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20134L2551997-01-16016 January 1997 Rev 0 to Integrated Plan for Improvement of Mgt Stds at Connecticut Yankee Nuclear Power Station ML20134L2701997-01-0303 January 1997 Rev 0 to Design Control Process ML20134L2511996-12-31031 December 1996 Rev 0 to Integrated Plan for Improving CA Program at Connecticut Yankee ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14627, Reactor Containment Bldg ILRT Rept. W/1993-09-30030 September 1993 Reactor Containment Bldg ILRT Rept. W/ B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20057A6241993-08-31031 August 1993 Core Xviii Startup Physics Test Rept ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution B14554, Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation1993-08-0909 August 1993 Proposed Tech Spec 3/4.4.1 Re Reactor Coolant Loops & Coolant Circulation ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20046A4651993-07-21021 July 1993 Proposed Tech Specs Re Radioactive Liquid Effluent Monitoring Instrumentation ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20046C1421993-07-0909 July 1993 Rev 12 to Response to Loss of Secondary Heat Sink ML20045D8531993-06-22022 June 1993 Proposed TS Changes to Include Augmented Erosion/Corrosion Program for Piping in AFW Bldg & Related Piping B14450, Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences1993-05-31031 May 1993 Proposed Tech Specs Page 3/4 4-17 Re RCS Pressurizer Code Safeties Lift Tolerences ML20036B9811993-05-28028 May 1993 Proposed Tech Specs SR 4.6.1.2,citing 10CFR50,App J,Which Incorporates Total Time Method & Mass Point Method for Calculating Containment Integrated Leakage Rates B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-061993-05-19019 May 1993 Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06 ML20045H2271993-05-18018 May 1993 Rev 2 to Nuclear Engineering & Operations (Neo) Procedure Neo 2.35, Pep Verification & Validation Program ML20044E4131993-05-17017 May 1993 Proposed Tech Specs Re Fire Protection ML20045G7991993-05-0707 May 1993 Rev 1 to Project Plan,Cyap Seismic Upgrade Program for Svc Water Sys,Feedwater Sys & Main Steam Sys Outside Containment B14461, Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop1993-05-0404 May 1993 Proposed TS 3/4.7.1 Re self-actuation & Remote Actuation Function of Safety Valves & Table 3.7-1, Steam Line Safety Valves Per Loop 1999-08-24
[Table view] |
Text
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4 Docket'No.'50-213 E14540-w Haddam Neck Plant Proposed Revision to Technical Specifications Radioactive Liquid _ Effluent Monitoring Instrumentation Markup Pages
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July'1993
@ta-9307280147 930721-PDR ADOCK 05000213-
- P-PDR (9% _
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l 2 6 1990 TABLE 3.3-9 M
RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION
.8
2 INSTRUMENT OPERABLE ACTION g.
1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING AUT0f% TIC TERMINATION OF RELEASE a.
Waste and Recycle Test Tank 1
46 Discharge Line b.
Steam Generator Blowdown Line*
1 47-2.
GROSS RADI0 ACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Service Water Effluent Line 1
48 w
3.
FLOW RATE MEASUREMENT A
a.
Waste.and Recycle Test Tank Discharge Line 1
49 b.
Steam Generator Blowdown Line N.A.
c.
Discharge-Canal N.A.
3Ig
- a. -
'M Automatic ter-%2tien of bl6edeva requirement w!! become effective epen completier of preposed-
-5.
modificatier te provide automatic te = %2 tier.
Nor APPucSLC WH'W f rJ - MOOC I cA f k
. Flow is determined by the use of valve curves for the purpose of. determining flows only.
Discharge canal flow is determined by the use of pump curves.
y (9) kh fM TABLE 4,3-7 RADI0 ACTIVE'LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS
_g M
CilANNEL R
CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.
GROSS RADI0 ACTIVITY HONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION
.0F RELEASE
-a.
Waste ~and Recycle Test Tank _ Discharge Line D(1)
P R(2)
Q(3).
b.
Steam Generator Blowdown Line*
D(I)
H R(2)
Q(3) 2.
GROSS RADI0 ACTIVITY HONITORS PROVIDING Y
ALARM B"" PST PROVIDING AUTOMATIC 0
TFRMIN; A. JF RELEASE a.
ervice Water Effluent D(1)
H R(2)-
Q(3)
Line 3.
FLOW' RATE HEASUREHENT is a.
Waste and Recycle Test Tank j
Discharge'Line.
D(1)
N.A.
R N.A.
a B.
Stean: Generator Blowdown Line 0(5)
N.A.
N.A.
N.A; p
c.
Discharge Canal.:
D(4)
N.A.
N.A.
N.A.
.m L.^utematic terminat4cn of'blewdowh' requiremc9t "!11 become effectivt upon-completion of c preW
--medification t0-provide cutomatic..tcr:-inction. Moi' A?pUcobt u.Ade.. m roor>6 5 - or fo;
gae.+
.ag g
w we 93
-%.+
W..
9 Docket No. 50-213 I
B14540.
Haddam Neck Plant Proposed Revision to Technical. Specifications Radioactive Liquid Effluent Monitoring Instrumentation Retyped Pages
. z
- t i
I t
j I
July 1993' I
i 1
i i
e
TABLE 3.3-9 iE RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION-E3 -
3E; MINIMUM #
z INSTRUMENT OPERABLE ACTION R
1.
GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC-TERMINATION OF RELEASE a
Waste and Recycle Test Tank 1
46 Discharge Line b.
Steam Ganerator Blowdown Line*
1 47 2.
GROSS RADI0 ACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Service Water Effluent 'Line 1
48 3.
FLOW RATE MEASURFMENT u,
1.
a.
Waste and Recycle Test Tank Discharge Line.
I 49 b.
Steam Generator Blowdown-Line N.A.
c.
1 Discharge Canal N.A.
E lF
~
- Not. applicable while in' Mode 5 or 6.'
o Flow is determined by the use of valve curves for the: purpose of determining -flowsLonly.
if;
.Discht rge canal' flowLis determined' by the useiof. pump curves.
.. Q
.mm c
s hm+.
Sv m
M-$ew r
7 r
h':
r TABLE 4.3-7
- - g g RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1
- :8 CHANNEL
^
E CHANNEL SOURCE CHANNEL FUNCTIONAL R. INSTRUMENT CHECK CHECK CALIBRATION TEST I.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION 0F RELEASE a.
Waste and.-Recycle Test Tank Discharge Line D(I)
P R(2)
Q(3) b.
Steam Generator Blowdown Line*'
D(1)
M R(2)
Q(3)
R 2.
GROSS-RADI0 ACTIVITY' MONITORS PROVIDING
^
' ALARM'BUT NOT PROVIDING AUTOMATIC Y'
TERMINATION OF RELEASE-O a.
Service Water Effluent D(1)
M
-R(2)
Q(3)
Line 3.
FLOW RATE MEASUREMENT a.
Waste and Recycle Test Tank
.p Discharge Line-0(1)
N.A.
R N.A.
k.
B.
Steam Generator Blowdown Line.
.D(5)
N.A.
N. A.-
-N.A.
c.
Discharge' Canal
,D(4)~
- N.A.
N.A.
N.A.
- g.
-u Not.applicab.le while in MODE-5 or 6.
- l..
m