ML20237E085

Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT

ML20237E085
Person / Time
Site:	Pilgrim
Issue date:	08/24/1998
From:	BOSTON EDISON CO.
To:
Shared Package
ML20237E083	List: ML20237E082 ML20237E085
References
NUDOCS 9808280240
Download: ML20237E085 (16)

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ATTACHMENT C

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Revised Technical Specification Paaes TS Page 3/4.5-10 (with TS 3/4.5.F.1 changes)

TS Page B3/4.5-22 (with B3/4.5 Bases changes)

TS Page B3/4.5-23 (with B3/4.5 Bases changes)

TS Page B3/4.5-24 (page no. change only)

TS Page 3/4.9-1 (no TS changes, reformatted)

TS Page 3/4.9-2 (no TS changes, reformatted)

TS Page 3/4.9-3 (no TS changes, reformatted)

TS Page 3/4.9-4 (with TS 3.9.B.1 changes)

TS Page 3/4.9-5 (with TS 3.9.B.4 changes)  !

l' TS Page 5.0-9 (with TS 5.5.7 added)

TS Page 5.0-10 (page no. change only)

TS Page 5.0-11 (page no. change only)

TS Page 5.0-12 (page no, change only) .;

TS Page 5.0-13 (page no change only) 1 TS Page 5.0-14 (page no. change only)  !

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Page1ofI l 9808280240 980024 PDR ADOCK 05000293 p PDR t

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.5 CORE AND CONTAINMENT 4.5 COHE AND CONTAINMENT COOLING SYSTEMS (Cont) COOLING SYSTEMS (Cont)

F. ' Minimum Low Pressure Coolina and F. Minimum Low Pressure Coolina and Diesel Generator Availability Diesel Generator Availability

1. During any period when one 1. When it is determined that one emergency diesel generator EDG is inoperable, within 24  !

(EDG) is inoperable, continued hours, determine that the reactor operation is permissible operable EDG is not inoperable l only during the succeeding 72 due to a common cause failure,

'[ hours unless such EDG is sooner made operable, provided OR l that all of the low pressure core and containment cooling perform surveillance 4.9.A.1.a systems shall be operable, and for the operable EDG' I the remaining EDG shall be AND operable in accordance with 4.5.F.1. If this requirement within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once every 8 cannot be met, an orderly hours thereafter, verify correct shutdown shall be initiated and breaker alignment and indicated the reactor shall be placed in power availability for each the Cold Shutdown Condition offsite circuit.

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

' 2. Confirm the Station Black Out The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO can be extended to 14 days provided, in Diesel Generator (SBO-DG) has been demonstrated operable addition to the above within the preceding 7 days requirements, the Station Black l Out Diesel Generator is verified OR operable in accordance with 4.5.F.2. within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of declaring an

2. Any combination of inopere.ble EDG inoperable, perform a components in the core and surveillance to demonstrate that containment cooling systems ,he SBO-DG is operable, shall not defeat the capability of the remaining operable AND components to fulfill the cooling functions. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of demonstrating the SBO-DG operability as specified

3. When irradiated fuelis in the above and once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reactor vessel ard the reactor is thereafter, verify normal breaker in the Cold Shutdown condition, conhgwadon.

both core spray systems, the LPCI and containment cooling systems may be inoperable, provided no work is being done which has the potential for f draining the reactor vessel.

4. During a refueling outage, for a period of 30 days, refueling operation may continue provided that one core spray system or the LPCI system is operable or Specification 3.5.F.5 is met.

Amendment No. 3/4.5-10 i

l Minimum Ltw Prscaura Cooling (nd Dimi Grn:ratar Availability 3/4.5.F i B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS 3/4.5.F. Minimum Low Pressure Cooling and Diesel Generator Availability

' BASES l

BACKGROUND The purpose of Specification 3/4.5.F is to assure that adequate core I cooling equipment is available at all times. If, for example, one core j spray were out of service and the diesel which powered the opposite I core spray were out of service, only 2 LCPI pumps would be available. {

lt is during refueling outages that major maintenance is performed and l during such time that all low pressure core cooling systems may be out of service. This specification provides that should this occur, no work will be performed on the primary system which could lead to draining the vessel. This work would include work on certain control rod drive components and recirculation system.

Specification 3.4.F.5 allows removal of one CRD mechanism while the torus is in a drained condition without compromising core cooling capability. The available core cooling capability for a potential draining of the reactor vessel while this work is performed is based on an estimated drain rate of 300 gpm if the control rod blade sealis unseated. Flooding the refuel cavity and dryer / separator pool to elevation 114'-0" corresponds to approximately 305,000 gallons of watcr and will provide core cooling capability in the event leakage from the control rod drive does occur. A potential draining of the reactor vessel (via control rod blade leakage) would allow this water to enter into the torus and after approximately 243,000 gallons have accumulated (needed to meet minimum NPSH requirements for the LPCI and/or core spray pumps), the torus would be able to serve as a common suction header. This would allow a closed loop operation of the LPCI system and the core spray system (once re-aligned) to the torus. In addition, the other core spray system is lined up to the condensate storage tanks which can supplement the refuel cavity and dryer / separator pool water to provide core flooding, if required.

ACTION The maximum allowed out-of-service (OOS) time for one EDG is 14 days, provided that one EDG and the SBO-DG are operable, in addition to all of the low pressure core and containment cooling systems as specified in 3.5.F.1. If the SBO-DG is determined to be inoperable, the maximum allowed OOS time for one EDG is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. A 24-hour LCO will control the plant for cold shutdown if the SBO-DG becomes inoperable anytime after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during a 14-day EDG LCO.

SURVEILLANCE The SBO-DG shall be determined to be operable as defined below for extending the 3 days OOS time to 14 days for an EDG. The SBO-DG is operable if a surveillance was completed within the lasi seven days before extending to a 14-day OOS; otherwise, a surveillance must be I completed to demonstrate that the SBO-DG is operable. The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period allows the operators to complete the required SBO-DG surveillance using the 23Kv offsite power source and to notify Commonwealth Electnc of the needed use of the 23Kv line in the testing configuration. The SBO-DG is operable if it is capable of

-PNPS B3/4.5-22 Amendment No.

Minimum Lew PrIs:ura Cooling gnd Dirrdi G nir;t r Avillibility 3/4.5.F B 3/4.5 CORE Ai4D CONTAINMENT COOLING SYSTEMS SURVEILLANCE energizing the safety bus associated with the inoperable EDG. Within

-(contiriued) one hour of demonstrating SBO-DG operability and once every eight hours thereafter, the normal breaker configuration for energizing the safety bus associated with the inoperable EDG should be verified. The SBO-DG is a non safety-related, manually started,2000KW generator and is not a qualified replacement for an EDG.

3/4.5.G. Deleted I

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PNPS B3/4.5-23 Amendment No.

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l Miint:ninca cf Fill:d DI:chIrg; Pips 3/4.5.H B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS 3/4.5.H. Maintenance of Filled Discharge Pipe

• BASES BACKGROUND If the discharge piping of the core spray, LPCI system, HPCI, and RCIC are not filled, a water hammer can develop in this piping when the pump and/or pumps are started. An analysis has been done which shows that if a water hammer were to occur at the time at which the system were required, the system would still perform its design function. However, to minimize damage to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system is in an operable condition. ,

l SURVEILLANCE An acceptable method of ensuring that the lines are fullis to vent at the high points. The monthly frequency is based on the gradual nature of void buildup in the ECCS piping, the procedural controls, and operating experience.

PNPS B3/4.5-24 Amendment No. l

LilblTING CONDITIONS FOR OPERATIONSURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

! Aoolicability Applicability I

Applies to the auxiliary electrical power Applies to the periodic testing system. requirements of the auxiliary electrical j systems.

Obiective: Obiective To assure an adequate supply of Verify the operability of the auxiliary electrical power for operation of those electrical system.

systems required for safety.

Specification Specification:

A. Auxiliary Electrical Eauipment A. Auxiliary Electrical Eauipment i

Surveillance The reactor shall not be made critical unless all of the following conditions are satisfied: 1. Diesel Generators

1. a. Each diesel generator shall be At least one offsite transmission line and the startup transformer are manually started and loaded available and capable of nce each month to automatically supplying auxiliary demonstrate operational power to the emergency buses. The ' ha

[eadi"gn nue br a east a 9 e

2. An additional source of offsite hour period at rated load.

l po consisting of one of the During the monthly generator test the diesel generator

a. A transmission line and starting air compressor shall shutdown transformer be checked for operation and capable of supplying power to its ability to recharge air the emergency 4160 volt receivers. The operation of buses. the diesel fuel oil transfer pumps shall be demonstrated,

b. The main transformer and and the diesel starting time to unit auxiliary transformer reach rated voltage and available and capable of frequency shall be logged, supplying power to the j emergency 4160 volt buses. b. Once per operating cycle the l

condition under which the j 3 Both diesel generators shall be diesel generator is required l

operable. Each diesel generator will be simulated and test shall have a minimum of 19,800 conducted to demonstrate that gallons of diesel fuel on site. It will start and accept the emergency load within the specified time sequence. The results shall be logged.

I PNPS 3/4.9-1 Amendment No. l l

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM A. Auxiliary Electrical Equipment (Cont) A. Auxiliary Electrical Eauipment

- Surveillance (Cont)

1. Verifying de-energization of the emergency buses and load shedding from the emergency buses.

2. Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency buses with permanently connected loads, energizes the auto-connected emergency loads through the Mad sequence, and operates L r 2 5 minutes while its generator is loaded with the emergency loads.

During performance of this surveillance verify that HPCI and RCIC inverters do not trip.

The results shall be logged.

c. Once per operating cycle with the diesel loaded per 4.9.A.1.b verify that on diesel generator trip, secondary (offsite) AC power is automatically connected within 11.8 to 13.2 seconds to the emergency service buses and emergency loads are energized through the load sequencer in the same manner as described in 4.9.A.1.b.1.

The results shall be logged.

l l PNPS 3/4.9-2 Amendment No.

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LlhllTING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM A. Auxiliarv Electrical Eauipment (Cont) Auxiliary Electrical Eauipment Surveillance (Cont)

4. 4160 volt buses A5 and A6 are energized and the associated 480 d. Once a month the quantity of volt buses are energized. diesel fuel available shall be logged.

5. The station and switchyard 125 and 250 volt batteries are operable. e. Once a month a sample of diesel Each battery shall have an fuel shall be checked for quality in operable battery charger. accordance with ASTM D4057-81 or D4177-82. The quality shall be i

6. Emergency Bus Degraded Voltage within the acceptable limits '

Annunciation System as specified specified in Table 1 of ASTM in Table 3.2.B.1 is operable. D975-81 and logged.

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7. Specification: 2. Station and Switchyard Batteries Two redundant RPS Electrical a. Every week the specific gravity, the Protection Assemblies (EPAs) shall voltage and temperature of the be operable at all times on both pilot cell and overall battery voltage inservice power supplies. shall be rneasured and logged. j Action b. Every three months the measurements shall be made of

a. With one EPA on an inservice voltage of each cell to nearest 0.1 power supply inoperable, volt, specific gravity of each cell, continued operation is and temperature of every fifth cell.

permissible provided that the These measurements shall be EPA is returned to operable logged.

status or power is transferred to a source with two operable c. Once each operating cycle, the EPAs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If this stated batteries shall be subjected requirement cannot be met, to a Service Discharge Test (load trip the power source. profile). The specific gravity and voltage of each cell shall be

b. With both RPS EPAs found to determined after the discharge and be inoperable on an inservice logged.

power supply, continued operation is permissible, d. Once every five years, the stated provided at least one EPA is batteries shall be subjected to a restored to operable status or Performance Discharge Test

. power is transferred to a (capacity). This test will be source with at least one performed in lieu of the Service operable EPA within 30 Discharge Test requirements of minutes. If this requirement 4.9.A.2.0 above.

cannot be met, trip the power source.

NOTE: Only applicable if tripping the power source would not result in a scram, i.

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-PNPS 3/4.9-3 Amendment No.

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LlhllTING CONDITIONS FOR OPERATIONSURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICA'L SYSTEM B. Operation with Inocerable Eauipment Auxiliarv Electrical Eauipment Surveillance (Cont)

Whenever the reactor is in Run Mode or Startup Mode with the reactor not in a 3 Emergency 4160V Buses A5-A6 Cold Condition, the availability of electric Degraded Voltage Annunciation power shall be as specified in 3.9.B.1, System.

3.9.B.2, 3.9.B.3, 3.9.B.4, and 3.9.B.5.

a. Once each operating cycle,

1. From and after the date that calibrate the alarm sensor.

incoming power is not available from the startup or shutdown b. Once each 31 days perform a transformer, continued reactor channel functional test on the operation is permissible under this alarm system.

condition for:

c. In the event the alarm system

a. 3 days with the startup is determined inoperable transformer inoperable under 3.b above, commence logging safety related bus E voltage every 30 minutes until

b. 7 days with the shutdown such time as the alarm is transformer inoperable restored to operable status.

During this period, both diesel 4. RPS Electrical Protection generators and associated Assemblies emergency buses must remain operable, a. Each pair of redundant RPS EPAs shall be determined to

2. From and after the date that be operable at least once per incoming power is not available 6 months by performance of from both startup and shutdown an instrument functional test.

transformers, continued operation is permissible, provided both diesel b. Once per 18 months each generators and associated pair of redundant RPS EPAs emergency buses are remain shall be determined to be operable, all core and containment operable by performance of cooling systems are operable, an instrument calibration and reactor power levelis reduced to by verifying tripping of the 25% of design and the NRC is circuit breakers upon the notified within one (1) hour as simulated conditions for required by 10CFR50.72. automatic actuation of the protective relays within the

3. From and after the date that one of following limits:

the diesel generators or associated emergency bus is made or found to Overvoltage s 132 volts be inoperable for any reason, Undervoltage 2108 volts continued reactor operation is Underfrequency 257Hz permissible in accordance with Specifications 3.4.B.1,3.5.F.1, 3.7.B.1.c, 3.7.B.1.e, 3.7.B.2.c, and 3.7.B.2.e if Specification 3.9.A.1 and 3.9.A.2.a are satisfied.

l PNPS 3/4.9-4 Amendment No.

LlhilTING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILLARY ELECTRICAL SYSTEM B. Operation with Inoperable Eauioment A. Auxiliary Electrical Eauioment Surveillance (Cont)

4. From and after the date that one of the diesel generators or associated emergency buses and either the shutdown or startup transformer power source are made or found to be inoperabia for any reason, continued reactor operation is l permissible for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided:

a. The startup transformer and both offsite 345kV transmission lines are available and capable of automatically supplying auxiliary power to the emergency 4160 volt buses, I B

b. The 23kV transmission line and associated shutdown transformer are available and capable of automatically

supplying auxiliary power to the emergency 4160 volt buses

5. From and after the date that one of the 125 or 250 volt battery systems

is made or found to be inoperable for any reason, continued reactor operat;on is permissible during the succeeding three days within l electrical safety considerations,

, provided repair work is initiated in l the most expeditious manner to return the failed component to an operable state, and Specification

!: 3.5.F is satisfied.

l l 6. With the emergency bus voltage

, less than 3958.5V but above l 3878.7V (excluding transients) )

l during normal operation, transfer l the safety related buses to the

! diesel generators, if grid voltage continues to degrade be in at least Hot Shutdown within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and in Cold Shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> unless the grid conditions improve.

PNPS 3/4.9-5 Amendment No.

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l Programs and Manuals 1 5.5 I i

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5.5 Programs and Manuals 5.5.7 l Configuration Risk Manaaement Proaram (CRMP) l l

CRMP provides a proceduralized risk-informed assessment to manage the risk  ;

associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed allowed outage time has been granted. {

l The CRMP includes the following elements:

a. Provisions for the control and implementation of a Level 1 at power internal event PRA-informed methodology. The assessment is capable of evaluating the applicable plant configuration.

b. Provisions for performing an assessment prior to entering the LCO Action Statement for preplanned activities.

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c. Provisions for performing an assessment after entering the LCO Action Statement for unplanned entry into the LCO Action Statement activities.

d. Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action Statement.

e. Provisions for considering other applicable risk significant contributors j such as Level 2 issues and external events, quantitatively or qualitatively.

PNPS 5.0-9 Amendment No. l l

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Reporting Requirements 5.6

,5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements i

The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Occupational Radiation Exposure Report A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (including description), waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket  !

dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.

Small exposures totaling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major wmk functions. The report shall be submitted by April 30 of each year.

5.6.2 Annual Radiological Environmental Operatina Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in

- 10 CFR 50, Appendix 1, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shallinclude a

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summary of the results of analyses of all radiological environmental samples ano of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing usults. The missing data shall be submitted in a supplementary report as soon as possible.

l (continued)

PNPS 5.0-10 Amendment No.

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Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a by May 15th of each year.

The report shallinclude a summary of the quantities of radioactive liquid and gasecus effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and process control procedures and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix 1,Section IV.B.1.

5.6.4 Monthly Operatina Reports Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the .

calendar month covered by the report. l 1

5.6.5 Core Operatina Limits Report (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. Table 3.1.1 - APRM High Flux trip level setting

2. Table 3.2.0 -APRM Upscale trip level setting

3. 3.11.A - Average Planar Linear Heat Generation Rate (APLHGR)

4. 3.11.B - Linear Heat Generation Rate (LHGR)

5. 3.11.C -Minimum Critical Power Ratio (MCPR)

6. 3.11.D - Power / Flow Relationship During Power Operation

7. 4.2 - Reactor Core

b. The analytical methods used to determine the core operating limits 1 shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. NEDE-24011 P-A," General Electric Standard Application for Reactor Fuel," (the approved version at the time the reload analyses are performed shall be identified in the COLR).

(continued)

PNPS 5.0-11 Amendment No.

Reporting R:quiremnnts 5.6

. 5.6 Reporting Requirements L 5.6.5 (continued)

2. NEDC-31852P, " Pilgrim Nuclear Power Station SAFER /GESTR-LOCA Loss of Coolant Accident Analysis", dated September,1990 (the approved version at the time the reload analyses are performed shall be identified in the COLR), and

3. NEDC-31312-P, " ARTS Improvement Program Analyses for

( Pilgrim Nuclear Power Station", dated September 1987, (the

! approved version at the time the reload analyses are performed shall be identified in the COLR).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

,. d. The COLR, including any midcycle revisions or supplements, shall be

! provided upon issuance for each reload cycle to the NRC.

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i PNPS 5.0-12 Amendment No. l I

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High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS l 5.7 High Radiation Area 1

5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mrem /hr but < 1000 mrem /hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics personnel) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 5; 1000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the RWP.

5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels 21000 mrem /hr shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Nuclear Watch Engineer on duty or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by (continued)

PNPS 5.0-13 Amendment No.

High Radiation Area -l

. 5.7 5.7 High Radiation Area

-_5.7.2 (continued) personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area. j 5.7.3 _ For individual high radiation areas with radiation levels of > 1000 mrem /hr, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that cannot be continuously guarded, and where no enclosure can be reasonably 1 constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

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(continued) l PNPS 5.0-14 Amendment No.

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