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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
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4.
I PLANT SYSTEMS 3/4.7.9 SNUBBERS, 1
LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers shall be OPERABLE. The only snubbers excluded from this requirement are,those installed on nonsafety-related systems and then only if their' failure or failure of the system on which they are installed, would have no adverse effect on'any safety-related system.
APPLICABILITY: MODES 1,.2, 3 cnd 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9.c on'the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
jil$VEILLANCE REOUIREMENTS
- 4. 7. 9 - Each snubber shall be demonstrated OPERABLE by perfornance of the following augmented inservice inspection program, a.
Visual Inspections The first inservice visual inspection of snubbers shall be performed after June 3, 1982 but before December 3, 1982 and shall include all snubbers. If less than two (2) snubbers are found inoperable during the-first inservice visual inspection, the second inservice visual.
inspection shall be performed 12 months 1 25% from the date of the first inspection. Otherwise subsequent visual inspections shall be performed in accordance with the following schedule:
I No. Inoperable Snubbers Subsequent Visual per inspection Period Inspection Period *#
0 18 months i 25%
4 1
12 months 1 25%
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6 rionths + 25%
3, 4 124 days 1 25%
5,6,7 62 days i 25%
8 or more 31 days 1 25%
<j The snubbers may be categorized into two groups: Those accessible l
i and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.
- The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
Yankee Rowe 3/4 7-27 AmendmentNo.#1,//
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PLANT SYSTEMS SURVEILLANCE REOU QEMENTS (Continugd)
Snubbers that are especially difficult to remove or in high radiation zones during shutdown shall also be included in the representative sampic.*
'In addition to the regular sample, snubbers which failed.the previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a failed L
snubber,-then both the failed snubber (if it is repaired and F(,'
installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for i
the re-sampling.
II If any snubber selected for functional _ testing either fails-to b
lockup or fails to move, i.e., frozen in place, the cause will'be
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evaluated and if caused by_ manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall.bc independent of the requirements stated above_for snubbers not meeting the
-functional test acceptance criteria.
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For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the anubber(s). The purpose of this engineering evaluation shall be to t
1 determine if the components supported-by the snubber (s)_were K
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adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.-
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Mechanical Snubbers Functionni Test Acceptance Criteria b
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The mechanical snubber functional test shall verify that 1.
The force that initiates free movement of the snubber. rod in cither tension or compression is less than the specified maximum drag force. Drag force shall not have increased more than 50% since the last functional' test.
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- 1 Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a F
justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all
. design conditions at either the completion of their fabrication or at a l
subsequent date.
Yankee Rowe 3/4 7-29 Amendment No. H. //
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ptANT SYSTEMS f'
G SURVEILLANCE REQUIREMENTS (Continued)'
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Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and t
compression.
3.
~ Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load the ability of the snubber to withstand load without displacement shall be i
verified.
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Snubber Service Life Monitoring A record of the service life'of each snubber, the date at' which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.n.
1 Concurrent with the first inservice' visual inspection and at least once per 18 nonths thereafter, the installation and nmintenance records for each snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded prior to the next scheduled L
snubber service life review, the snubber service' life-shall be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled
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service life review. This re-evaluation, replacement, or
-reconditioning shall be indicated.ir. the records.
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Yankee Rowe 3/4 7-29a AmendmentNo.#I,71,//
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PLANT SYSTEMS.
j BASES i-3/4.7.8 ENVIRONMENTAL MONITORIhG l
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3/4.7.9 SNUBBERS I
All snubbers are required OPERABLE to ensure that-the structural f
integrity of the reactor coolant system and all other safety-related systems i
L is maintained during and following a seismic or other event initiating dynamic l
p loads.-
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The vistal inspection frequency is based upon nmintaining a constant l-level of snu1ber protection to systems. Therefore, the required inspection interval srsies inversely with the observed snubber f ailures and is determined t
by the runber of inoperable snubbers found during an inspection.
Inspections perfermed before that interval has elapsed may be used as a new reference point to cetermine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less.25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inapection interval will override the previous schedule, r
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'When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are'those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or l
are similarly located or exposed to the same environmental conditions such es temperature, radiation, and vibration.
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YANKEE-ROWE B 3/4 7-6 AmendmentNo.[f,//,//
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ADMINISTRATIVE CONTROLS y
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Records of the service lives of all snubbers, including the date at 3
which the service life commences and associated installation and-I
. maintenance records.-
6.11 RADIATION PROTECTION PROGRAM I-Procedures'for personnel radiation protection shall be prepared consistent
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with requirements of 10 CFR Part 20 and shall be approved, maintained and adhered,to for'all operations. involving personnel radiation exposures.
6.12 HICH RADIATION AREA-
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6.12.1 Paragraph 20.203 " Caution signs. labels, signals, and controls".
In I
i lieu of:the " control device" or " alarm signal" required by paragraph.
g 20.203(c)(2), each high radiation area in which the intensity of radiation is.
P 1000 mrem /hrLor less shall be barricaded and conspicuously posted as a high p
radiation area, and entrance thereto shall be controlled by requiring. issuance L
of a Radiation Work Permit.* An individual or group of individuals permitted to enter such areas shall be provided with one or more of the followings a.
A radiation monitoring device which continuously indicates the l
radiation dose rate in the area.
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A radiation monitoring device which continuously integrates the radiation dose rate in the area, and alarms when a preset integrated l
dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been.
l established and personnel have been made knowledgeable of them.
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A Health Physics qualified individual (i.e., qualified in radiation c.
protection procedures), with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and who will perform radiation surveillance at the frequency specified fn the RWP. The l
surveillance frequency will be established by the Plant Health Physicist.
i Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection dutiec.
providing they are following plant radiation protection procedures for entry into high radiation areas.
s YANKEE-ROWE 6-24 Amendment No. 71. 80. M j
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