Text

Tech Specs 3.1 & 4.1 Re Reactivity Control Sys Charging Pumps Refueling Limiting Condition for Operation
	ML20002A391
Person / Time
Site:	Yankee Rowe
Issue date:	11/21/1977
From:	; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20002A387	List: ML20002A386; ML20002A391;
References
	NUDOCS 8011170051
	Download: ML20002A391 (21)
	v • d • e

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - REFUELING QMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTICN:

With less than tso charging pumps OPERABLE, suspend all operations involving CORE A'.TERATICNS or positive reactivity changes until at least tso charging pumps are restored to CPERABLE status.

i SURVEILLANCE RECUIREMENTS 4.1.2.4 At least the above required charging pumps shall be demonstrated OPERABLE at least once per 31 days by:

a.

Starting (unless already operating) each pump frca the control rocm, b.

Verifying that each pump develops a discharge flow > 26 gpm, and c.

Verifying pump operation for at least 15 minutes.

YANKEE-ROWE 3/4 1-13 8 011170 O(d

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REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTCOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 At least one charging pump in the boron injection flow path required by Specification 3.1.2.2 shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTICN:

With no charging pump OPERABLE, suspend all operations involving positive reactivity changes until at least one charging pump is restored to OPERABLE status.

SURVEILLANCE REGUIREMENTS 4.1.2.5 At least the above required charging pump shall be demonstrated OPERABLE at least once per 31 days by:

Starting (unless already operating) the pump frcm the control a.

room, b.

Verifying that the pump delivers a flow > 26 gpm to the Main Coolant System, and c.

Verifying pump operation for at least 15 minutes.

a YANKEE-ROWE 3/4 1-14 Amendment No. 35 January 31, 1977

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REACTIVITY CONTROL SYSTEMS CHARGINC PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.5 At least two charging pumps shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps ts OPERA 3LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least MOT STANC3Y and borated to a SHUTDOWN MARGIN (all control rods inserted) equivalent to at least 5", ak/k at 200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS

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4.1.2.6 - At least two charging pumps shall be demonstrated OPERABLE at least once per 31 days on a STAGGERED TEST BASIS by:

a.

Starting (unles: already operating) each puma frcm the contrcl room, b.

Verifying that each pump delivers a flow > 26 gpm to the Main Coolant System, c.

Verifying that each pump operates for at least 15 minutes, and d.

Verifying that the pump suction and discharge valves are open.

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YANKEE-ROWE 3/4 1-15 Amendment No. 35 ff;---

January 31,197i I

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3 I-4 REACTIVITY CONTROL SYSTEMS BORIC ACID MIX TANK GRAVITY FEED CONNECTION - SHUTCONN AND REFUELING LIMITING CONDITION FOR OPERATION

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1 3.1.2.7 The boric acid mix tank gravity feed connection shall be OPERABLE if the flow path from the boric acid mix tank of Specificatien n

3.1.2.1 or 3.1.2.2a is OPERABLE.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no mix tank gravity feed connection OPERABLE as required to complete the flow path of Specification 3.1.2.1 or 3.1.2.2a, sus:end all operations involving CORE ALTERATIONS or positive reactivity changes until the boric

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q acid mix tank gravity feed connection is restored to GPERABLE status.

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.1 SURVEILLANCE REOUIREMENTS

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.Li 4.1.2.7 The above requ' ired -boric acid mix tank gravity feed connection shall be demonstrated OPERABLE:

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,r 1 a.

At least once per 7 days by:

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Cycling each testable power operated valve in the flow path through at least one complete cycle of full travel.

2.

Verifying that each valve (manual or power operated) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months, during shutdown, by demonstrating the gravity feed connection flow to be > 26 gpm.

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l MAIN COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

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> 45 CPS, be in at least HOT STANDBY within the next 6 Fours.

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With more than two leaking incere detection system thimbles which are valved off but not plugged when in MODE 1, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDCWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

.1 SURVEILLANCE REOUIREMENTS

i-j 4.4.5.2 Main Coolant System leakages shall be demonstrated to be within each of the above limits by;

.ij a.

Monitoring the containment atmosphere particulati radioactiv-

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ity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except when a Main Coolant System water inventory has not been perfonned within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , then monitor the containment atmosphere particulate r.adica.ctivity monitor at least once per hour.

l b.

Monitoring the contair, ment drain tank monitoring system at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

t c.

Performance of a Main Coolant System water inventory balance at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during steady state operation, y

d.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

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'4 YANKEE-ROWE 3/4 4-11 Amendment No. 38 May 3,1977

MAIN COOLANT SYSTEM CH'EMISTRY a

2R LIMITING CONDITION FOR OPERATICN 3.4.6 The Main Coolant System chemistry shall be maintained within the limits specified in Table 3.4-1.

i APPLICABILITY: At all times.

ACTION:

MODES 1, 2, 3 and 4

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With any one or more chemistry parameter in excess of its a.

Steady State Limit but within its Transient Limit, restore the Parameter to within its Steady State Limit withid 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months anc in ' COLD 3

. SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With any one or more. chemistry parameter in excess of itr, Transient Limit, Ee in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and i

in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

At all other times 4' "

With the concentration of either chloride or fluoride in the Main Coolant System in excess of its Steady State Limit for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or in excess of its Transient Limit, reduce the pressurizer

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. pressure to < 500 psig, if applicable, and perform an engineering evaluation to determine the effects of the cut-of-limit condition on the structural integrity of the Main Coolant Systen.: determine that the Main Coolant System remains acceptable for continued operations prior to increasing the pressurizer pressure above 500 psig or pricr to proceeding to MODE 4.

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SURVEILLANCE REOUIREMENTS

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4.4.6 The Main Coolant System chemistry shall be determined to be

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.gq within the limits by analysis of those parameters at the frequencies specified in Table 4.4-1.

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YANKEE-ROWE 3/4 4-12 hk=E m-

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j EMERGENCY CCRE CCOLING SYSTEMS ECCS SUBSYSTEMS LIMITING CONDITION FOR CPEPATION 3.5.2 The ECCS subsystems shall be OPERABLE with:

a.

Three OPERABLE independent ECCS safety injection subsystems with each subsystem comprised of:

1 One OPERA 3LE high pressure safety injection pump, 2.

One OPERABLE low pressure safety injection pump, 3.

An OPERASLE flow path capable of taking suction frem I

the safety injection tank on a safety injection signal.

b.

An OPERABLE ECCS recirculation subsystem with two OPERABLE purification pumps and an OPERABLE flow path capable of taking l

suction frcm the containment sump and recirculating to the safety injection header.

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c.

An OPERABLE ECCS long term hot leg injection subsystem with at least two OPERABLE fixed speed charging pumps and an OPERABLE 8

flow path capable of taking suction from the ECCS recircula-tion subsystem and discharging to the Main Coolant System da j

hot leg.

APPLICABILITY: MODES 1, 2, 3*, 4* and 5*

ACTION:

a.

With one ECCS safety injection subsystem or che purification pump or one fixed speed charging pump inope able, restore the inoperable subsystem or pump to GPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HGT SHUTCOWN with Main Coolant pressure

< 1000 psig within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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b.

In the evei i..ie ECCS is actuated and injects water into the Main Coolant System a Special Report shall be prepared and submitted to the Ccmmission pursuant to Specifisation 6.9.6 within 90 days describing the circumstances of the actuation and the total accumulated actuaticn cycles to date. The pro-visions of Specification 3.0.3 are not applicable.

' Main coolant pressure > 1000 psig.

YANKEE-ROWE 3/4 5-3

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EMERGENCY CORE COOLING SYSTEMS _

SURVELLANCE RE0VIREMENTS Each ECCS safety injection subsystem, the recirculation sub-4.5.2 system, and the long term hot leg injection subsystem shall be demon-strated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by:

a.

Verifying that each high pressure safety injection pump:

1.

a)

Starts (unless already operating) from the control room.

b)

Develops a discharge pressure of > 850 psig on re-circulation flow.

c)

Operates for at least 15 minutes.

Verifying that each low pressure safety injection pump:

2.

a)

Starts (unless already oper?.tirg) from the control

room, b)

Develops a discharge pressure cf > 250 psig on T

recirculation flow through CS-MOV 532.

c)

Operates for at least 15 minutes.

3.

Verifying that each purification pump:

a)

Starts (unless already operating) frem the control room.

b)

Develops a discharge pressure 3,80 psig'in normal purification system service.

c)

Operates for at least 15 minutes.

4 Verifying that each fixed speed charging pump:

a)

Starts (unless already operating) from the control room.

b)

Delivers a flow 3,25 gpm to the, Main Coolant System, and c)

Operates for at least 15 minutes.

35 quendment Novanuary al, 1977 YANKEE-ROWE 3/4 5-4

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Table 4.7-4 EllVIR0tlMEllTAL M0tlITORIllC PROGRAM 5

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A Humber of Environs Parameter Sample Points Sample Frequency Extent of Analyses

.:u di Air 6

Continuous sampling, weekly collection Gross beta I-131 Quarterly composite Gamma Spectroscopy, SR-89,90*

River Water 3

Monthly Gross beta, gansna spectroscopy Ouarterly composite 11-3, Sr-89.90*

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Ground Water 2

Quarterly Gross beta, gamma spectroscopy, 11-3, S r-89,90*

Once per 3 years Ra-226 R

Food 2

Annually (llarvest Time)

Gamma spectroscopy,1-131 on

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green leafy portion of vegeta'-

Dt bles, Sr-89,90*

Direct External Radiation 23 11onthly Integrated gamma exposure -

two TLD readouts Soll 11 Once per three years Ganina spectroscopy, Sr-89,90*

E li a '4 ra wS Vegetation 6

Once per 92 days, April through Gansna spectroscopy 5

December

$5 N="w River Sediments 5

Semi-annually Gamma spectroscopy, Sr-89,90*

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ENVIRONMENTAL HONITORING PROGRAM a-en Number of Envirens Parameter Sample Points Sample Frequency Extent of Analyses Milk 3

Monthl,y 1-131, gamma' spectroscopy, Sr-89,90 Fish 3

Semi-annually Gamma spectroscopy, Sr-89,90*

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7 Aquatic Plants 3

Semi-annually Gamms spectroscopy,Sr-89,90*

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Analysis whenever the plant-related Cs-137 concentration is 10X the non-plant-related Cs-137 concentration.

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i REFUELING OPERATIONS SHIELD TANK CAVITY MANIPULATOR CRANE OPERABILITY LIMITING CONDITION FOR OPERATION 3.9.6 Control rods and fuel assemblies shall be handled one-by-one with an OPERABLE shield tank cavity manipulator crane and universal handling tool with:

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a.

A minimum capacity of 900 pounds, and 4

b.

An overload cut off limit < 4800 pounds above base load.

l APPLICABILITY: During movement of control rods or fuel assemblies l

within the reactor pressure vessel.

2 ACTION:

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With the requirements for crane and handling tool OPERABILITY not satisfied, suspend use of the ino'perable manipulator crane or handling tool from operations involving the movement of control rods and fuel assemblies within the reactor-pressure vessel. The provisions of Specification 3.0.3 are not app'licable.

SURVEILLANCE REOUIREMENTS 1

4.9.6 The manipulator crane and handling tool used for movement of

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control rods or fuel assemblies within the reactor pressure vessel shall

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be demonstrated OPERABLE wi-thin <100 hours prior to the start of such operations by performing a load test of at least 900 pounds, demon-strating an automatic load cut off when the crane load exceeds 4800

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pounds above base' load, and verifying proper operation of,the handling

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tool.

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q YANKEE-ROWE 3/4 9-7 Amendment No. 33 December 29, 1976

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REFUELING OPERATIONS

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CRANE TRAVEL - SPENT FUEL PIT LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 900 pounds shall be prohibited from travei over the spent fuel pit except for the:

l a.

Spent fuel pit building roof hatches, b.

Spent fuel inspection stand, c.

Fuel handling equipment, and d.

Spent fuel racks.

APPLICABILITY: With fuel assemblies in the spent fuel pf't.

ACTION:

With the requirements of the above specification not satisfied, place 4

the crane load in a' safe condition. The provisions of Specification 3.0.3 are not applicable.

J SURVEILLANCE REOUIREMENTS s.N ~

4.9.7 Loads in excess of 900 pounds shall be prevented from traveling over the spent fuel pit by administrative control except that the:

a.

Spent fuel pit building roof hatches, the spent fuel inspection

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stand; the fuel handling equipment and the spent fuel racks, may travel over the ' spent fuel pit in accordance wi.th approved writtan pr]cedures, b.

Spent fuel storage racks and the spent fuel ins;;ction stand shall

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be prevented from traveling over fuel assemblies in The spent fuel pit by administrative control, anJ qsa c.

Fuel handling equipment when moved for maintenance shall be pre-

. vented from traveling 'over fuel assemblies in the spent fuel pit by

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administrative control.

r-YANKEE-ROWE 3/4 9-8 Amendment No. 39 June 3,1977 pi em M

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3/4.9 REFUELING OPERATIONS BASES l

3 /4. 9.1 REACTIVITY

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The limitations on reactivity ensure that: 1) the reactor will remain substantially subcritical during CORE ALTERATIONS, and 2) a uniform baron concentration is maintained for reactivity control in the j

water volume having direct access to the reactor vessel.

3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in tne reactivity condition of the core during CORE ALTERATIONS. One monitor is acceptable whenever CORE ALTERATIONS are not in prcgress on the basis of the core stable reactivity condition.

i 3/4.9.3 OECAY TIME The minimum requirement for reactor tubcriticality prior to move-ment of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the accident analyses.

3/4.9.4 CONTAIhMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERASILITY ensure that a release of radioactive material within con-tainment will be restricted frem leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radio-active material release frem a fuel element rupture based upon the lack of containment p. essurization potential while in the REFU,ELING MODE.

3/a.9.5 CCMMUNICATIONS The requirement for cohmunications capability ensures that re-fueling s tatf or, personnel can be promptly informed of significant changes in the facilicy status or core reactivity conditions during CORE ALTERATIONS.

YANKEE-ROWE B 3/4 9-1 Amendment No. 33 December 29, 1975 1:

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REFUELING OPERATf0NS 7

BASES l

3/4.9.6 SHIELD TANK CAVITY MANIPULATOR CRANE OPERABILITY The OPERASILITY requirements for the manipulator cranes ensure that: 1) the manipulator crane and universal handling tool will be used for movenent of control rods and fuel asserablies, 2) each crane and tool has sufficient load capacity to lift a control rod or fuel assembly, and

3) the core internals and pressure vessel are protected frca excessive lifting force in the event they are inadvertently engaged during lifting operations.

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3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT E

The restriction on movement of loads in excess of the ncminal weight of a fuel assembly over fuel assemblies in the spent fuel pit ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assenbly, and (2) any possible-distortion of the fuel in the storage tanks will not result in a critical array. This assumation is consistent with the activity release assumed in the accident analysis.

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Handling of the spent fuel pit building roof hatches for infrequent

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transfers of spent fuel racks by administrative control will assure safe

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handling of the roof hatches. The restricticn of movement of the spent fuel storage racks and spent fuel inspecton stand over spent fuel ensures that a rack or stand cannot be dropped on spent fuel. Dropping of a rack or stand from a maximum height will not result in loss of integrity h..

of the fuel pit floor. Handling of the fuel handling equipnent for infrequent maintenance by administrative ' ontrol will ensure the safe c

handling of any fuel handling components. Handling of fuel casks over the spent fuel pit is not permitted until such time as NRC has reviewed and approved the spect fuel cask drop evaluation, 3/4.9.8 COOLANT CIRCULATION The requirement that the Shutdown Cooling System be in operation is y, _

consistent with the assumptions in the analysis of the baron dilution 55" accident and prevents local variations in boron concentrations,'thus

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minimizing the effects of an inadvertent boron dilution.

It also as-n._

sures that sufficient cooling capacity is available to remove decay heat ar.d maintain the water in the reactor pressure vessel below 140*F as ig; required during the REFUELING MODE.

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YANKEE-ROWE B 3/4 9-2 Amendment No. 39

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REFUELING OPERATIONS BASES 3/4.9.9 CONTAINMENT PURGE FAN SHUTOOWN SYSTEM The OPERABILITY of this system ensures that the contair. ment purge fan can be shutdown upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material fecm the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT F'JEL P!T The restrictions on minimum water level ensure that sufficient water depth is available to remove 99". of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the acciden:

analysis.

j 3/4.9.12 SPENT FUEL PIT BUILDING ISOLATION The requirements for spent fuel. pit building isolation ensure that radioactive material released from an irradiated fuel ass.embly will be remain within the spent fuel pit area. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with

..e assum::-

fons of the accident analyses.

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a DESIGN FEATURES' l

CONTROL R00 5.3.2 The reactor core shall contain 24 control rods. At least twenty-two control rods shall contain a ncminal 90 inches of absorber material.

The nominal values of this absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. Up te two control rods may have four 90" blades of Hafnium as the absorber. All control rods shall be clad with stainless steel.

5.4 MAIN COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Main Coolant System is designed and shall be maintained:

a.

In accordance With the code requirements specified in ASME Boiler and Pressure Vessel Code,Section VIII, including all addenda through 1956, and the ANSI (formerly ASI) Standards, Power Piping Code, B31.1,1955 Edition,*and B16.5,1957 Edition, with allcwance for normal degradation pursuant to the applicable Surveillance Requirements, b.

For a pressure of 2500 psig, and c.

For a temperature of 650'F, except for the pressurizer which is 668'F.

VOLUME 5.4.2 The total water and steam volume of the Main Coolant System is 2940 cubic feet.

5.5 METEOROLOGICAL 70'JER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1 The new and spent fuel storage racks are designed and shall be maintained with a center-to-center distance between fuel assemblies placed in the storage racks to ensure a k equivalent to <0.95 with the new or spent fuel storage areas flood $dfwith unborated water. The ku Re,e,rta iH'ti es.of <0.95 includes a conservative allowance of 3% ak/k for YANKEE-ROWE 5-4 Amendment No. 39 Jur.e 3, 1977

= _ _

=-..

DESIGN FEATURES DRAINAGE 5.6.2 The spent fuel storage. pool is designed and shall be maintained I

to prevent inadvertent draining of the pool.

CAPACITY 5.6.3 The spent fuel pit is designed and shall be maintained with a storage capacity limited to no more than 391 fuel assemblies.

[

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT

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5.7.1 The components identified in Table 5.7-1 are designe ' and shall be maintained within the cyclic or transient limits of Table L -1.

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..(7 YANXEE-ROWE 5-5 Amendment No. 33 Decemoer 29, 1975'

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5 TAllt E 5.7.1 M

N COMP 0flEllT CYCLIC OR TRAfr :EllT LIMITS a

$1 E

CYCLIC OR DESIGN CYCLE C0f1P0flEllT TRAtlSIEllT LIMIT OR TRAtlSIEllT Reactor Pressure Vessel 200 heatup and cooldown cycles 70*F to 534"F to 70*F

> 50*F/ hour and < 100*F/ hour.

6 sh L

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30

'8 'a"

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'ADMIflISTR ATIVE CONTROLS f.

Unless otherwise authori:ed by the Ccr. mission, the licensee shall not assign protection factors in excess of those specified in Table 6.12-1 in selecting and using respiratory protective equipment.

REVOCATION 6.12.3 The specifications of Section 6.12 shall be revoked in their entirety upon adoption of the proposed change to 10 CFR 20, Section 20.103, which would make such provisions unnecessary.

I 6.13 HIGH RADIATION AREA 6.13.1 Paragraph 20.203 " Caution signs, labels, signals, and controls."

!n lieu of the " control device" or " alarm signal" required by paragraph 20.2"3(c)(2;,

each high radiation area in which the intensity of radiation is 10C0 mren/hr or less shall be barricaded and conspicuously posted as a high radiaticn area and entrance thereto shall be controlled by requiring issuance f a Radiati:n horkPermit.* An individual or group of individuals semitted to enter such areas shall be provided with one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the Area.

l-the radiation dose rate in the area and alarms when a preset b.

A radiation monitoring device which continuously integrates integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in tne area have been established and personnel have been made know-ledgeable of them.

c.

A health physics qualified individual (i.e., qualified in i

radiation 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 perf::rm j

radiation surveillance at the frequency specified in the RWP.

The surveillance frequency will be established by the Plant Health Physicist.

The above procedure shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.

In addition,

locked doors shall. be provided9:o prevent unauthori:ed entry into such areas and the key shall be maintained under the administrative control of the shift supervisor on duty and/or the Plant Health physicist.

Health Physics personnel shall be exempt from the RWP issuance require ent during the performance of their assigned radiation protection duties, :ro-viding they are following plant radiation protection proc.edures for en ry into high radiation areas.

YANKEE-ROWE 6-27 Amendment No. *C June 16,1977 i

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1; TABLE 6.12-1 x',"

PROTECTION FACTORS FOR RESPIRATORS

'E

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PROTECTION FACTORS (2)

GUIDES TO SEl.ECTION 0F EQUIPMENT

PARTICULATES AND 11UREAU OF MINES / NATIONAL INSTITUTE VAPORS AND GASES-FOR OCCUPATIONAL SAFETY AND llEALTil EXCEPT TRITIUM APPROVALS (*or schedule superseding for -

DESCRIPTION (7)

MODES (l)

OXIDE (3) equipment type listed.)

i I.

AIR-PURIFYING RESPIRATORS I

Faceplece, hal f-mask (),

NP S

30 CFR Part 11 Subpart X Facepiece, full flP 100 30 CFR Part 11 Subpart K II. ATHOSPilElN-SUPPLYING

. Mm(n RESPIRAT0l[

"'/u 1.

Airline respirator Facepiece, hal f-mask CF 100 30 CFR Part 11 Subpart J facepiece, full CF 1,000 30 CFR Part 11 Subpart J Faceplece, full D

100 30 CFR Part 11 Subpart J kh Facepiece, full PD 1,000 30 CFR Part 11 Subpart J ma llood s

CF (S) 30 CFR Part 11 Subpart K e

Suit CF (5)

(6) i Memps 2.

Sel f-contained breathino apparatus (SCBA),

Facepiece, full D

100 30 CFR Part 11 Subpart it Facepiece, fdll P0 1,000 30 CFR Part 11 Subpart 11

. i oa j

,S Facepiece, full R

100 30 CFR Part 11 Subpart 11 l

n o

$5i III. COMBINATION RESPIRATOR Any combination of air-Protection factor for j

purifying and atmosphere-type and mode of opera-30 CFR Part 11 5 ll.63(b) i supplying respirator tion as listed above i

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