Proposed Tech Spec Changes,Revising Table 3.3-4, Radiation Monitoring Instrumentation, Table 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements & Tech Spec 3.3.3.2, Instrumentation-In-Core Detection SysML20133J800 |
Person / Time |
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Site: |
Yankee Rowe |
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Issue date: |
10/15/1985 |
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From: |
YANKEE ATOMIC ELECTRIC CO. |
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To: |
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Shared Package |
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ML20133J793 |
List: |
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References |
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RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8510210099 |
Download: ML20133J800 (8) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20043E6231990-05-31031 May 1990 Proposed Tech Specs 3.10.3 & 3.10.4 Re Limiting Conditions for Operation ML20034B3071990-04-19019 April 1990 Proposed Tech Specs Re HPSI & LPSI Pump Surveillance Frequency ML20042E2211990-04-12012 April 1990 Proposed Tech Specs,Addressing Administrative Changes ML20006A4651990-01-18018 January 1990 Proposed Tech Specs Re HPSI Throttle & Pressurizer Auxiliary Spray Mods & Surveillance Requirements for ECCS ML20005F1431990-01-0505 January 1990 Proposed Tech Specs Re Instrumentation Sys ML19332D1161989-11-22022 November 1989 Proposed Tech Specs Incorporating Wording from Generic Ltr 84-13 Which Removes Table 3.7.4 Re safety-related Mechanical Snubbers ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20210A5041987-01-29029 January 1987 Proposed Tech Specs Re Extension of Cycle 18 in-core Instrumentation Sys to Cycle 19 ML20213A4431987-01-22022 January 1987 Proposed Tech Specs,Providing Flexibility in Areas Governing Integrity Testing of Steam Generator Tubes ML20215N6281986-10-22022 October 1986 Proposed Tech Spec 4.5.2.b.4,increasing Allowable Open Time for LPSI Min Recirculation Line Valve CS-MOV-532 to 120 Minutes Per Wk ML20197A7611986-10-20020 October 1986 Proposed Tech Specs,Allowing for Performance of 10CFR50.59 Reviews for Future Core Reloads ML20211E8091986-10-0909 October 1986 Proposed Tech Spec Table 4.3-1, Reactor Protective Sys Instrumentation Surveillance Requirements ML20204F7191986-07-31031 July 1986 Proposed Changes to Tech Specs 3.3.3.2,4.2.1.2,4.2.2.1, 4.2.2.2 & 4.2.3.2 Re Operation of in-core Instrumentation Sys ML20211K7501986-06-24024 June 1986 Proposed Changes to Tech Specs to Allow Performance of 10CFR50.59 Reviews for Future Core Reloads ML20151U5571986-02-0505 February 1986 Proposed Tech Specs,Per Generic Ltr 84-43, Reporting Requirements of 10CFR50... & Generic Ltr 85-19, Reporting Requirements on Primary Coolant Iodine Spikes & Supporting LER Sys Mods ML20136J3981986-01-0808 January 1986 Proposed Changes to Tech Spec Table 3.6-1,replacing Manual Containment Isolation Valve W/Blank Flange ML20141G3461986-01-0606 January 1986 Proposed Tech Spec Changes,Permitting Filing of Supplemental Dose & Meteorological Summary Rept within 150 Days of Jan 1 Each Yr ML20138N3131985-10-31031 October 1985 Proposed Tech Spec Changes Per NUREG-0737,Item II.F.1.6, Containment Hydrogen Monitors 1999-04-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20197D4341997-12-31031 December 1997 Rev 1 to Ynps License Termination Plan ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20141F6391997-05-15015 May 1997 License Termination Plan for Yankee Nuclear Power Station ML20198G6381997-02-0707 February 1997 Rev 12 to Ynps Off-Site Dose Calculation Manual ML20138Q5301996-10-31031 October 1996 Rev 11 to Off-Site Dose Calculation Manual ML20198S6131993-12-31031 December 1993 Partially Deleted Rev 9 to Edcr 93-303, Vessel Internals Segmentation Component Removal Program 1995 ML20198S5681993-08-0202 August 1993 Partially Deleted Rev 6 to Edcr 93-303, Reactor Vessel Internals Segmentation Component Removal Program 1993 ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20058D8451990-10-29029 October 1990 Separate Rept Re Local Leak Rate Test Results from Core 19/20 Refueling Outage ML20058D8421990-06-30030 June 1990 June 1990 Reactor Containment Bldg Integrated Leak Rate Test & Periodic Local Leak Rate Tests ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20043E6231990-05-31031 May 1990 Proposed Tech Specs 3.10.3 & 3.10.4 Re Limiting Conditions for Operation ML20034B3071990-04-19019 April 1990 Proposed Tech Specs Re HPSI & LPSI Pump Surveillance Frequency ML20042E2211990-04-12012 April 1990 Proposed Tech Specs,Addressing Administrative Changes ML20006A4651990-01-18018 January 1990 Proposed Tech Specs Re HPSI Throttle & Pressurizer Auxiliary Spray Mods & Surveillance Requirements for ECCS ML20005F1431990-01-0505 January 1990 Proposed Tech Specs Re Instrumentation Sys ML19332D1161989-11-22022 November 1989 Proposed Tech Specs Incorporating Wording from Generic Ltr 84-13 Which Removes Table 3.7.4 Re safety-related Mechanical Snubbers ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20244D3931989-04-11011 April 1989 Core 20 Startup Program for Yankee Nuclear Power Station ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20154L9791988-03-0606 March 1988 Rev 6 to Yankee Nuclear Power Station Offsite Dose Calculation Manual ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses 1999-04-23
[Table view] |
Text
n.
ATTACHMENT A The following Technical Specification pages have been revised and are attached:
PAGE 3/4 3-18 3/4 3-20 3/4 3-21 3/4 3-23 3/4 3-30 3/4 3-31 6-22 e
P
1 TABLE 3.3-4 RADTATION MONITORING INSTRUMENTATION N
?
8 MINIMUM CHANNELS APPLICABLE ALARM MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.
AREA MONITORS (a) Spent Fuel Pit Area 1.
Fuel Manipulator 1
(1) 1 5 mR/hr or 2 x 1.0 - 50 mR/hr*
11 background, which-ever is greater (b) Containment 1.
Fuel Mcnipulator 1
(1) i 10 mR/hr or 2 x 1.0 - 1000 mR/hr*
12 background, which-u, 3:
ever is greater
[
7 2.
High Range 1
1,2,3,4 1 5 R/hr 1.0 - 10 R/hr 15 oo (Also Accident -
Emergency Monitors) 2.
PROCESS MONITORS (a) Containment
+
1.
Main Coolant System 1
1,2,3,4 NA 10 - 106 cpm 13 Leakage Air Par-ticulate Monitor 4
(b) Radioactive Liquid g,
Monitors S
1.
Steam Generator 1(2) 1, 2, 3, 4 1 80 cps or 2 x 10 - 106 14 cpm Blowdown Monitors background, whichever i
is greater z
S
- Indicated upper end of measurement range is minimum required. Actual measurement range may exceed that L
h(
stated.
Ns
w TABLE 3.3-4 (Continued)
TABLE NOTATION (1) When handling ircadiated fuel, control rods or sources.
(2) Per stesa generator in a non-isolated loop.
ACTION STATEMENTS Action 11 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.
Action 12 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend all operations involving CORE ALTERATIONS.
Action 13 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1.
Action 14 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, provide an OPERABLE temporary continuous monitor within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Action 15 -
With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s),
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and
- 1. either restore the inoperable Channel (s) to OPERABLE status within seven days of the event, or
- 2. prepare and submit a special report to the Commission pursuant to Specification 6.9.6 within fourteen days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
YANKEE-ROWE 3/4 3-20 Amendment No. 58, SS i
i
I TABLE 4.3-3 N
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS M
i:!
A O
MODES CHANNEL IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE q
INSTRUMENT CHECK CALIBRATION TEST REQUIRED 1.
AREA MONITORS 8
(a) Spent Fuel Pit Area 1.
Fuel Manipulator S
R M
(b) Containment g
1.
Fuel Manipulator d
S R
h y
2.
High Range N
(Also Accident
~
Emergency Monitors S
R R
1,2,3,4 2.
PROCESS MONITORS (a) Containment 1.
Main Coolant System Leakage Air Particulate Monitor S
R M
1,2,3,4 (b) Radioactive Liquid Monitor g
1.
Steam Generator Blowdown
R H
1,2,3,4 I
S en When handling irradiated fuel, control rods or sources.
i
INSTRUMENTATION INCORE DETECTION SYSTEM LIMITING CONDITIONS FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:
a.
At least twelve (12) neutron detector thimbles OPERABLE.
b.
A minimum of two (2) OPERABLE neutron detector thimbles per core quadrant, and c.
Sufficient OPERABLE movable neutron detectors, drive and readout equipment to map these thimbles.
APPLICABILITY: When the incore detection system is used for core power distribution measurements.
ACTION With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.2 The incore neutron detectors shall be demonstrated OPERABLE by normalizing each detector output to be used within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use for core power distribution measurements.
YANKEE-ROWE 3/4 3-23 Amendment No. g, g, g, g
TABLE 3.3-7 Accident Monitoring Instrumentation Total No.
Minimum Channels Instrument Of Channels Operable 1.
Pressurizer Water Level 2
1 2.
Auxiliary Feedwater Flow Rate 4
3 3.
Main Coolant Syttem Subcooling 1
1 Margin Monitor 4.
PORY Position Indicator (Acoustic 1
1 Accelerometer) 5.
PORY Position Indicator (Temperature 1
0 Indication, RTD) 6.
PORV Block Valve Position Indicator 1
1 7.
Safety Valve Position Indicator 1
1 (Acoustic Accelerometer) 8.
Safety Valve Position Indicator 1
0 (Temperature Indication, RTD) 9.
Containment Water Level 2
1 (Wide-Range) 10.
In Core Thermocouple Channels 8
1 in each (Core Exit Thermocauples) of 3 Core Quadrants 11.
Containment Pressure (Wide-Range) 2 1
12.
Reactor Vessel Head Thermocouples 2
-l j
YANKEE-ROWE 3/4 3-30 AmendmentNo.[
TABLE 4.3-5 Accident Monitoring Instrumentation Surveillance Requirements channel channel Instrument Check Calibration 1.
Pressurizer Water Level M
R 2.
Auxiliary Feedwater Flow Rate M
R 3.
Main Coolant System Subcooling M
R Margin Monitor 4.
PORV Position Indicator (Acoustic M
R Accelerometer) 5.
PORY Position Indicator (Temperature M
R Indication, RTD) 6.
PORV Block Valve Position Indicator M
R 7.
Safety Valve Position Indicator M
R (Acoustic Accelerometer) 8.
Safety Valve Position Indicator M
R (Temperature Indication, RTD) 9.
Containment Water Level M
R (Wide-Range) 10.
In Core Thermocouple Channels M
R (Core Exit Thermocouples) 11.
Containment Pressure (Wide-Range)
M R
12.
Reactor Vessel Head Thermocouples M
R YANKEE-ROWE 3/4 3-31 Amendment No. yI
ADMINISTRATIVE CONTROLS The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to-the OFF-SITE DOSE CALCULATION MANUAL.(ODCN), as well as a listing of new locations for dose calculations'and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.
6.9.6 Special reports shall.be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
a.
(Deleted),
b.
ECCS Actuation, Specifications 3.4.2 and 3.5.3.
c.
Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.3.
d.
Sealed Source leakage in excess of limits Specification 3.7.6.
e.
Fire Detection Instrumentation, Specification 3.3.3.4.
f.
Fire Suppression Systems, Specifications 3.7.10.1, 3.7.10.2, 3.7.10.3, 3.7.10.5 and 3.7.10.6.
g.
Liquid Effluents Specifications 3.11.1.2 and 3.11.1.3.
h.
Gaseous Effluents, Specifications 3.11.2.2, 3.11.2.3 and 3.11.2.4.
i.
-Total Dose, Specification 3.11.4.
J.
Radiological Environmental Monitoring, Specification 3.12.1.
k.
Radiation Monitoring, Specification 3.3.3.1.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspection repair and replacement of principal items of equipment related to nuclear safety, c.
ALL REPORTABLE OCCURRENCE reports submitted to the CONNISSION.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
AmendmentNo.[,g,[
YANKEE-ROWE 6-22
-