Text

Proposed Tech Specs for Implementation of New 10CFR20 Requirements
	ML20046B606
Person / Time
Site:	Hatch
Issue date:	07/30/1993
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20046B604	List: ML20046B603; ML20046B606;
References
	NUDOCS 9308050224
	Download: ML20046B606 (22)
	v • d • e

,

l Enclosure 2 '

Edwin I. Hatch Nuclear Plant.

Request to Revise Technical Specifications: .

Implementation of the New 10 CFR 20 Requirements

i Proposed Technical Specifications Chances Unit 1 Revised Paaes* ,

3.15-22 ,

6-21 Unit 2 Revised Paaes*

B 3/4 11-2 6-19 r p

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Supersedes proposed changed Technical Specifications pages submitted by !

Georgia Power Company letter dated January 15, 1993.

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HL-3360 005871 E2-1 9308050224 930730 iT '

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RADI0 ACTIVE EFFLUENTS BASES l-3/4.15.1.3 L10VID WASTE TREATMENT This specification transferred to the ODCM per NRC Generic Letter 89-01.

3/4.15.1.4 LIOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in I the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting-concentrations would be less than 20=%mnt'the limits of 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2-(Column 2), at the nearest surface water supply in an UNRESTRICTED AREA.

3/4.15.2 GASE0US EFFLUENTS 3/4.15.2.1 DOSE RATE This specification transferred to the ODCM per NRC Generic letter 89-01.

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HATCH - UNIT 1 3.15-22 techsp\h\92-16UlB. pro /110

ADMINISTRATIVE CONTROLS to enter such areas shall be provided with or accompanied by one or more of the following: ,

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

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b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alares when a preset integrated dose is received. Entry into such areas with this monitoring device e.ay be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over '

the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physics supervision in the Radiation Work Permit.

InStri 1l -

6.12.2. The requirements of 6.12.1., above, shall also apply t ach area .

in which the intensity of radiation is greater than 1000 arem/h in i addition, locked doors shall be provided to prevent unauthorized e ry 3 1 n S e rt 2 }'

into such areas and the keys shall be maintained under the administrative i control of the Shift Supervisor on duty and/or the Laboratory Foreman on duty.

6.13. INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:

1) Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2) System leak test requirements, to the extent permitted by systes design and radiological conditions, for each system at a frequency not i to exceed refueling cycle intervals. The systems subject to this testing j are (1) Residual Heat Removal, (2) Core Spray, (3) Reactor Water Cleanup, j (4) HPCI, and (5) RCIC. j 6.14. 10 DINE MDNITORING ~I The Itcensee shall implement a program which will ensure the capabilit o accurately determine the airborne iodine concentration in vital areas nder accident conditions. This program shall include the following:

1) Training of personnel,

2) Procedures for monitoring, and

3) Provisions for maintenance of sampling and analysis equipment.

IInsert 3 i >fr W Areas requiring personnel access for establishing hot shutdown condition.

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HATCH - UNIT 1 6-21 'techsp\h\92-16 Ult. pro /109

v Lnsert I high radiation

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Insert 2 e

but less than 500 rads in I hour."

Insert 3

Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates. .

- Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.

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RADI0 ACTIVE EFFlVENTS BASES ,

3/4.15.1.3 LIOVID WASTE TREATMENT This specification transferred to the ODCM per NRC Generic Letter 89-01.

3/4.15.1.4 LIOVID HOLDUP TANKS 1 Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2 (Column 2),

at the nearest surface water supply in an UNRESTRICTED AREA.

3/4.15.2 GASE0US EFFLVENTS 3/4.15.2.1 DOSE RATE This specification transferred to the ODCM per NRC Generic Letter 89-01. t I

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HATCH - UNIT 1 3.15-22 techsp\h\92-16U1B. pro /110 l

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@@(13TRAUVE CONTROLS i

to enter such areas shall be provided with or accompanied by one or more of ,

the following.

a. A radiation monitoring device which continuously indicates the !

radiation dose rate in the area. ;

b. A radiation monitoring device which 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 af ter the dose rate level in the area has been established and personnel have been made knowledgeable of them. :

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This ,

individual shall be responsible for providing positive control over ;

the activities within the area and shall perform periodic radiation - :

surveillance at the frequency specified by the facility Health !

Physics supervision in the Radiation Work Permit. !

6.12.2. The requirements of 6.12.1., above, shall also apply to each high !

radiation area in which the intensity of radiation is greater than .

I 1000 mrem /hr* but less than 500 rads in I hour.** In addition, locked doors ;

shall be provided to prevent unauthorized entry into such areas and the ,

keys shall be maintained under the administrative control of the Shift 7 Supervisor on duty and/or the Laboratory foreman on duty. .l t

6.13. INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a (

serious transient or accident to as low as practical levels. This program !

shall include the following

1) Provisions establishing preventive maintenance and periodic visual !

inspection requirements, and .i f

2) System leak test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency not . j to exceed refueling cycle intervals. The systems subject to this testing are (1) Residual Heat Removal, (2) Core Spray, (3) Reactor Water Cleanup, [

(4) HPCI, and (5) RCIC. !

6.14. IODINE MONITORING The licensee shall implement a program which will ensure the capability to !

accurately determine the airborne iodine concentration in vital areas"* under -l l accident conditions. This program shall include the following: -l

1) Training of personnel,

2) Procedures for monitoring, and ;

3) Provisions for maintenance of sampling and analysis equipment. ;

t

Measurement made at 30 centimeters from the radiation source er from any i surface that the radiation penetrates. {

- Hessurement made at 1 meter from the radiation source or from any surface i that the radiation penetrates.

- - Areas requiring personnel access for establishing hot shutdown condition. l HATCH - UNIT 1 6-21 techsp\h\92-16UIC. pro /109 f

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. 1 EADI0 ACTIVE EFFLUENTS I

BASES 3/4.11.1.3 LIOUID WASTE TREATMENT -

This specification transferred to the ODCM per NRC Generic t letter 89-01, 3/4.11.1.4 LIOUID HOLDUP TANKS Restricting the quantity of r-dioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than 3D:tust the limits of

10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2 (Column 2), at the nearest surface water supply in an ,

UNRESTRICTED AREA.

3/4.11.2 GASEOUS EFFLUENTS .

3/4.11.2.1 DOSE RATE This specification transferred to the ODCH per NRC Generic ,

Letter 89-01.

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t HATCH - UNIT 2 B 3/4 11-2 techsp\h\92-16U2E/48

l 1

ADMINISTRATIVE CONTROLS l to enter such areas shall be provided with or accompanied by one or more of the following:

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

b. A radiation monitoring device which 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 level in the area has been established and personnel have been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is ;

equipped with a radiation dose rate monitoring device. This i individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation ,

surveillance at the frequency specified by the facility Health Physics supervision in the Radiation Work Permit. l I wrt U 6.12.2 The requirements of 6.12.1, above, shall also apply to each(

area in which the intensity of radiation is greater than 1000 mrem /hrw In addition, locked doors shall be provided to prevent unauthorized lInsed 2]

entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Laboratory Foreman on duty.

6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program ,

shall include the following: l

1) Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2) System leakage test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency not to exceed refueling cycle intervals. The systems subject to this testing are (1) Residual Heat Removal, (2) Core Spray, (3) Reactor Water Cleanup, ,

(4) HPCI, and (5) RCIC. l IInsert 31 1

HATCH - UNIT 2 6-19 techsp\h\92-16U20. pro /47 1

i Insert I high radiation Insert 2 t

but less than 500 rads in I hour.*

Insert 3 ,

Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates. ;

- Measurement made at 1 meter from the radiation source or from any surface that the ;

radiation penetrates.

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Unit 2 -i Revised Pages ,

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RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIOUID WASTE TREAIBENI This specification transferred to the ODCM per NRC Generic Letter 89-01.

3/4.11.1.4 LIOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in -

the specified tanks provides assurance that in the event of an ,

uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2 (Column 2),

at the nearest surface water supply in an UNRESTRICTED AREA.

3/4.11.2 GASE0US EFFLUENTS ,

3/4.11.2.1 DOSE RATE I

This specification transferred to the ODCM per NRC Generic Letter 89-01.

)

HATCH - UNIT 2 B 3/4 11-2 techsp\h\92-16U2E/48 s = _ . . -- . ,

1 ADMINISTRATIVE CONTROLS to enter such areas shall be provided with or accompanied by one or more of the following: )

~

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

b. A radiation monitoring device which 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 level in the area has been established and personnel have been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physics supervision in the Radiation Work Permit.

l 6.12.2 The requirements of 6.12.1, above, shall also apply'to each high radiation area in which the intensity of radiation is greater than.

1000 mrem /hr* but less than 500 rads in I hour.** In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Laboratory Foreman on duty.

6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:

1) Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2) System leakage test requirements, to the extent permitted by system 1 design and radiological conditions, for- each system at a frequency not to exceed refueling cycle intervals. The systems subject to this. testing are (1) Residual Heat Removal, (2) Core Spray, (3) Reactor Water Cleanup, '

(4) HPCI, and (5) RCIC.

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Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.

- Measurement made t 1 meter from the radiation source or from any surface 1 that the radiation penetrates. ]

HATCH - UNIT 2 6-19 techsp\h\92-16U2D. pro /47 l

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Enclosure 3 Edwin I. Hatch Nuclear Plant Request to Rev'se Technical Specifications:

Implementation of the New 10 CFR 20 Requirements Summary Listino of Proposed Paaes

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i Unit 1 Submittal Date of Proposed Paae Latest Version i vi 9/21/92 ix 9/21/92 1.0-8 5/3/93 .:

1.0-9 1/15/93 3.2-18 10/14/92 3.14-1 9/21/92 3.14-2 thru 3.14-5 9/21/92 3.14-6 9/21/92 3.14-7 9/21/92 3.14-8 9/21/92 3.14-9 Enclosure 4 3.14-10 9/21/92 3.14-11 9/21/92 3.14-12 9/21/92 3.14-13 9/21/92 3.14-14 9/21/92 ,

3.15-1 9/21/92 3.15-2 thru 3.15-3 9/21/92 ,

3.15-4 9/21/92 ,

3.15-5 9/21/92 3.15-7 '9/21/92 3.15-8 5/3/93 3.15-9 9/21/92 3.15-10 9/21/92 3.15-11 9/21/92 3.15-12 9/21/92 :

3.15-13 9/21/92 3.15-14 9/21/92 ,

3.15-15 9/21/92 3.15-16 9/21/92 ;

3.15-17 9/21/92 3.15-18 5/3/93 ,

3.15-19 9/21/92 3.15-20 9/21/92 3.15-21 9/21/92 3.15-22 Enclosure 2 ;

HL-3360 ;

005871 E3-1 ,

Enclosure 3 Summary Listing of Proposed Pages Unit 1 Submittal Date of Proposed Pace latest Version 3.15-23 9/21/92 3.15-24 9/21/92 3.15-25 9/21/92 3.15-26 9/21/92 j 3.16-1 9/21/92 3.16-2 thru 3/16-10 9/21/92 3.16-11 9/21/92 3.16-12 9/21/92 ;

3.16-13 9/21/92 6-1 9/21/92 6-15 10/14/92 6-15a 5/3/93 6-15b 9/21/92 6-15c 9/21/92 6-15d 9/21/92 6-20 1/15/93 6-21 Enclosure 2 6-23 5/3/93 6-23a 3/26/93 6-23b 9/21/92 l

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I Enclosure 3 Summary Listing of Proposed Pages Unit 2 Submittal Date of Proposed Paae latest Version-V 9/21/92 ,

XI 9/21/92 ,

XVI 5/3/93 XVII 9/21/92 ,

1-7 5/3/93 1-8 1/15/93 3/4 3-44 10/14/92 .

3/4 3-60a 9/21/92 3/4 3-60b thru 3/4 3-60e 9/21/92 .

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3/4 3-60f Enclosure 4 3/4 3-609 9/21/92 >

3/4 3-60h 9/21/92 :

3/4 3-60i 9/21/92 :

3/4 3-60j 9/21/92 3/4 3-60k 9/21/92 3/4 11-1 9/21/92 3/4 11-2 thru 3/4 11-3 9/21/92 3/4 11-4 9/21/92 3/4 11-5 9/21/92 ,

3/4 11-7 9/21/92 3/4 11-8 5/3/93 3/4 11-9 9/21/92 3/4 11-10 9/21/92 3/4 11-11 9/21/92 !

3/4 11-12 9/21/92 ,

3/4 11-13 9/21/92 3/4 11-14 9/21/92 3/4 11-15 9/21/92 3/4 11-16 9/21/92 't 3/4 11-17 9/21/92' ,

3/4 11-18 5/3/93 3/4 11-19 9/21/92 3/4 11-20 9/21/92 3/4 12-1 9/21/92 B 3/4 3-5 9/21/92 :

B 3/4 11-1 9/21/92. i B 3/4 11-2 Enclosure 2 -

HL-3360 1 005871 E3-3 i

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I Enclosure 3 Summary Listing of Proposed Pages i

Unit 2 i Submittal Date of '

Proposed Paae latest Version B 3/4 11-3 9/21/92 ,

B 3/4 11-4 9/21/92

B 3/4 11-5 9/21/92 '

B 3/4 11-6 9/21/92 6-1 9/21/92 i 6-14 10/14/92 6-14a 5/3/93 ,

6-14b 9/21/92 6-14c 9/21/92 6-14d 9/21/92 a 6-18 1/15/93 6-19 Enclosure 2 >

6/22 5/3/93 6/22a 3/26/93 6-22b 9/21/92 .

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HL-3360-005871 E3-4 ,

Enclosure 4 Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Implementation of the New 10 CFR 20 Requirements Description of Chanaes to Previously Submitted Paaes Proposed changes to Unit 1, page 3.14-9, Amendment 110 were submitted by letter dated September 21, 1992. This page was revised by Amendment 185.

The proposed changes to this page delete three footnotes and Actions 104 and i

105. Since the changes made to this page by Amendment 185 add statements to Actions 104 and 105, these changes do not affect the proposed version.

However, Amendment 185 also added a statement to Action 106 which currently falls on page 3.14-10. Since the proposed changes delete Actions 104 and 105, there will be rors on page 3.14-9 for the statement added to Action 106.

l Therefore, the version neluded in this enclosure shows the changes made in l the original proposed version and also includes the statement which was added I

to Action 106 by Amendment 185. This statement allows for instrument surveillance testing.

Proposed changes to Unit 2, page 3/4 3-60f, Amendment 48 were submitted by ;

letter dated September 21, 1992. This page was revised by Amendment 125.

The proposed change to this page removed references to radioactive gaseous effluent monitoring instrumentation, and revised the specification such that only explosive gas monitoring instrumentation is addressed. Amendment 125 added Action "c" to allow for instrument surveillance testing. Therefore, i the version included in this enclosure shows the changes made in the original '

proposed version and also includes Action "c" which was added by Amendment 125.

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l HL-3360 005871 E4-1

TABLE 3.14.2-1 (SHEET 2 0F 2) l l EXPLOSIVE GAS MONITORING INSTRUMENTATION l Table Notations !

- During main condenser offgas treatment system operation.

ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may ;

continue provided:

(a) Gas samples are collected once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the ensuing 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or (b) Using a temporary hydrogen analyzer installed in the ,

offgas system line downstream of the recombiner, l hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . ,

I One instrument channel may be inoperable for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to perform required surveillances prior to entering other applicable actions. '

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1 HATCH-UNIT 1 3.14-9 techsp\h\92-11U18.185

INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION l ,

LIMITING CONDITION FOR OPERATION 3.3.6.10 The explosive gas monitoring instrumentation l ,

channels shown in table 3.3.6.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the ;

limits of Specification 3.11.2.6 are not exceeded. l APPLICABILITY As shown in table 3.3.6.10-1.

ACTION

a. With an explosive gas monitoring instrumentation l channel alarm / trip setpoint less conservative than a value that will ensure that the limits of 3.11.2.6 are met, without delay restore the l setpoint to a value that will ensure that the limits of Specification 3.11.2.6 are met or declare the channel inoperable and take the ACTION shown in table 3.3.6.10-1.

b. With the number of channels OPERABLE less than the minimum channels required by table 3.3.6.10-1, take the ACTION shown in table 3.3.6.10-1. Restore the inoperable i instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c. One instrument channel may be inoperable for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to perform required surveillances prior to entering other

. applicable ACTIONS.

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ;

SURVEILLANCE REOUIREMENTS 4.3.6.10 Each explosive gas monitoring instrumentation- l ,

channel shall be demonstrated OPERABLE by performance of '

the CHANNEL Ci!ECK, CHANNEL CALIBRATION, and CHANNEL l FUNCTIONAL TEST operations at the frequencies shown in table 4.3.6.10-1.

HATCH - UNIT 2 3/4 3-60f techsp\h\92-11028.125 1

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ML20046B606

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