Text

Amends 79 & 18 to Licenses DPR-57 & NPF-5,respectively, Incorporating Certain TMI-2 Lessons Learned Category a Requirements
	ML19340C223
Person / Time
Site:	Hatch
Issue date:	10/28/1980
From:	Reid R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19340C224	List: ML19340C223; ML19340C225; ML19340C229;
References
	NUDOCS 8011140267
	Download: ML19340C223 (24)
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",6, UNITED STATES 8

,o NUCLEAR REGULATORY COMMISSION h

WASHINGTON. D. C. 20555 t

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4 GEORGIA POWER COMPANY g

OGLETITORPE POWER CORPORATION MUNICIPAL ELETTR!l AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. l.

AMENDMENT TO FACILITY OPERATING LICENSE AiTiendment No. 79 License No. DPR-57 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Georgia Power Company, et al.,

(the licensee) dated September 15, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:

8011140 267

. The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1h Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing l

Attachment:

Changes to the Technical Specifications Date of Issuance: October 28, 1980 l

1 l

i 1

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ATTACHMENT TO LICENSE ANENDMENT tl0. 79 FACILITY OPERATING LICENSE NO. OPR-57 s

DOCKET NO. 50-321 4

J Replace the following pages of the Appendix "A" Technical Specifications The revised pages are identified by Amendment with the enclosed pages.

number and contain vertical lines indicating the area of change.

Insert Remove vi vi 3.2-22 3.2-22 3.2-23 3.2 23 3.2-48 3.2-48 6-4 6-4 6-6 6-6 6-21 6-21 i

1

___,._-__r..

Section Section Page LIMITING CONDITIONS FOR OPERATION SURVilLLANCE REQUIREMENI5 5.0-1 5.0 MAJOR DESIGN FEATURES 5.0-1 A.

Site 5.0-1 B.

Reactor Core 5.0-1 C.

Reactor Vessel 5.0-1 D.

Containment 5.0-1 E.

Fuel Storage 5.0-2 F.

Seismic Design 6-1 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 Responsibili ty 6-1 6.2 Organization

.6-6 '

6.3 Unit Staff Qualifications 6-6 6.4 Training 6-6 6.5 Review and Audit 6-12 6.6 Reportable Occurrence Action 6-12 6.7 Safety Limit Violation 6-13 6.3 Procedures 6-14 6.9 Reporting Requirements 6-18 6.10 Record Retention 6.11 Radiation Protection Program 6-20 6-20 6.12 High Radiation Area 6.13 Integrity of Systems Outside Containment 6-21 6-21 6.14 Iodine Monitoring 6.15 Environmental Qualification 6-22 Amendment No. p5, 79 y3

=

Table 3.2-11 INSTRUMENTATION WHICH PROVIDES SURVEILLANCE INFORMATION Required gm Ref.

Operable Q{

No.

Instrument Instrument Type and gg (a)

(b)

CMnnels Range Action Remarks

@M m:

1 Reactor Water Level (GF/MAC) 1 Recorder (c)

(d) 2 Indicator 0 to 60" (c)

(d)

E 2

Shroud Water Level 1

Recorder (c)

(d)

-d 1

Indicator +200" to +500" (c)

(d) 3 Reactor Pressure 1

Recorder (c)

(d) 2 Indicator 0 to 1200 psig (c)

(d)

T U

4.

Drywell Pressure 2

Recorder -5 to +80 psig (c)

(d) 5 Drywell Temperature 2

Recorder 0 to 500 F (c)

(d) 6 Suppression Chamber Air Temperature 2

Recorder 0 to 500 F (c)

(d) 7 Suppresciion Chamber Water Temperature 2

Recorder 0 to 2500F (c)

(d) u f

8 Suppr.3sion Chamber Water Level 2

Indicator 0 to 300" (c)

(d) y 2

Recorder 0 to 30" (c) (e)

(d) 9 Suppression (hamber Pressure 2

Recorder -5 to +80 psig (c)

(d) 10 Rod Position Information System (RPIS) 1 28 Volt Indicating Lights (c)

(d) 11 Hydrogen and Oxygen Analyzer 1

Recorder 0 to 52 (c)

(d) 12 Post LOCA Radiation Monitoring System 1

Recorder (c)

(d)

Indicator 1 to 106 R/hr (c)

(d) 13 Drywell/ Suppression Chamber Differential Pressure 2

Recorder -0.5 to 4 2.5 psid (c) (e)

(d) 14 a) Safety / Relief Valve Position Primary 1

Pressure Switch 4-100 psig (f)

Indicator b) Safety / Relief Valve Position Secondary 1 Temperature element 0-600 F (f)

Indicator

NOTES FOR TABLE 3.2-11 a.

The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be esti lished between items in Table 3.2-11 and items in Table 4.2-11.

g2

I b.

Liniting Conditions for Operation for the Neutron Monitoring System are listed in Table 3.2-7.

h-i S5 c.

From and after the date that one of these parameters is reduced to one indication, continued y

n 3: ::

operation is permissible during the succeeding thirty days unless such instrumentation is sooner Tg made operable.

U Continued operation is permissible for seven days from and after the date that one of these parameters is not indicated in the control room.

Surveillance of local panels will be substituted for indication in the control room during the seven days.

E d.

Drywell and Suppression Chamber Pressure are each recorded on the same recorders. Each output channel has its own recorder.

Drywell and Suppression Chamber air temperature and suppression chamber water temperature are all recorded on the same recorders.

Each output channel has its own recorder.

Each recorder y

takes input from several temperature elements.

Yg Hydrogen and Oxygen are indicated on one recorder. The recorder has two pens, one pen for each parameter.

Each channel of the post LOCA radiation monitoring system includes two detectors; one located in the drywell and the other in the suppression chamber.

Each detector feeds a signal to a separate log count rate meter. The neter output goes to a two pen recorder.

One high radiation level alarm is provided per channel and annuciation of alarm is provided in the control room, e.

In the event that all indications of this parameter is disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.

f.

If either the primary or secondary indication is inoperable, the torus temperature will be monitored least once per shift to observe any unexplained temperature increase which might be indicative at of an open SRV. With both the primary and secondary monitoring channels of two or more SRVs inoperable either restore sufficient inoperable channels such that no more than one SRV has both primary and secondary channels inoperable within 7 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Table 4.2-11 Check and Calibration Minimum Frequency for Instrumentation k _,

Which Provides Surveillance Information

(

R "_i Instrument Check Instrument Calibration g

Ref.

Iustrument Minimum Frequency Minimum Frequency gg No.

(c)

(b) 2g (a)

. c:

1 Reactor Water Level Each shift Every 6 months

'w-(GE/MAC)

M 2

Shroud Water Level Each shift Every 6 months 3

Reactor Pressure Each shift Every 6 months Each shift Every 6 months 4

Drywell Pressure Each shift Every 6 months 5

Drywell Temperature 6

Suppression Chamber Air Each shift Every 6 months Tempe'rature u

7 Suppression Chamber Water Each shift Every 6 months

f Temperature Each shift Every 6 months 8

Suppression Chamber Water Level Each shift Every 6 months 9

Suppression Caamber Pressure 10 Rod Position Information Each shift N/A System (PSIS)

Each shift Every 6 months 11 Hydrogen and Oxygen Analyzer 12 Post LOCA Radiation Each shifL Every 6 months 13 Drywell/ Suppression Chamber Each shift Every 6 months Differential Pressure 14 a) Safety / Relief Valve Position Pri-Monthly Every 18 months mary Indicator b) Safety / Relief Valve Position Monthly Every 18 months Secondary Indicator

TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION #

Condition of Unit 1 - Unit 2 in Reactor Power Operation, Hot Standby or Hot Shutdown Condition LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1, 2, 3 4&5 SOL **

2 Z*

OL**

3 2

Non-Licensed 3

3 Shitt Technical Advisor i

i Condition of Unit 1 - Unit 2 in Cold Shutdown Condition or Refuel Mode LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 S O L*

2 1*

OL**

2 Z

Non-Licensed 3

3 Shift Technical Advisor 1

None Condition of Unit 1 - No Fuel in Unit 2 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL 1

1*

2 1

OL Non-Licensed 2

1 Shift Technical Advisor 1

None

Does not include the Licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supe rvising CORE ALTERATIONS.

- Assumes each individual is licensed on both units.

Shift crew composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimun requirements of Table 6.2.2-1.

j PLANT llATCll UNIT 1 6-4 Amendment No. td, 79

ADMINISTRATIVE CONTROLS 6.3 ImIT STAFF QUALIFICATIONS 6.3 1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the llealth Physicist-Radiochemist who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor *who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Senior Methods and Training Specialist and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for fire protection shall be maintained under the direction of the Senior Regulatory Specialist and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for fire protection training sessions which shall be held at least once per 92 days.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)

FUNCTION 6.5.1.1 The PRB shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review Board shall be composed of the:

Cha irman:

Plant Manager Vice Chairman:

Assistant Plant Manager Member:

Operations Superintendent Member:

Superintendent Plan Engineer Services Member:

Maintenance Superintendent Member:

Senior Quality Control Specialist Member:

llealth Physicist-Radiochemist ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRD Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PRB activities at any one time.

The qualifications for the Shif t Technical Advisor apply af ter January 1,1981. l PLANT HATCll UNIT 1 6-6 Amendment No. ff, 79

ADMINISTRATIVE C0fGR01.

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

A radiation monitoring dev. ice which continuously indicates the a.

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 inte-grated 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 knowl-edgeable of them.

An individual qualified in radiation protection procedures who c.

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 Physicist 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 1000 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained unoer the administrative control of the Shif t Foreman on duty and/or the Plant Health Physicist.

6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAIUMENT 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 l

shall include the following:

1) Provisions establishing preventive maintenance and periodic visual inspec-tion requirements, and 2)

System leak 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 systens subject to this testing are (1)

Residual Heat Removal, (2) Core Spray, (3) Reactor Water Cleanup, (4) HPCI, i

and (5) RCIC.

6.14 IODINE fIONITORING Tb licensee ' hall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

under accident conditions. This program shall include the following:

1) Training of personnel,

2) Procedure. for monitoring, and

3) Provisions f40r maintenance of sanpling and analysis equipment.

Areas requiring personnel access for establishing hot shutdown condition.

IMTCH - UNIT 1 6-21 Amendment No. J4I, 79

[p ucg'o, UNITED STATES 8'

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NUCLEAR REGULATORY COMMISSION

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?g GEORGIA POWER COMPANY g

OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIL AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.18 License No. NPF-5 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Georgia Fower Company, et al.,

(the licensee) dated September 15, 1980, complies with the standards and requirements of tne Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements -

have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:

j

The Technical Specifications contained in Appendices A and B, as revised thmugh Amendment No. 18, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COP 911SSION l

pf..

Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications 4

Date of Issuance: October 28, 1980 l

i l

i

ATTACHMENT TO LICENSE AMENDMENT NO.18 FACILITY OPERATING LICENSE NO. NPF-5 e

D0CKET NO. 50-366 Replace the followinj pages' of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Over-leaf pages are included.

Insert Remove XVII (added) 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 6-4 6-4 6-5 6-5 6-19 6-19 6-20(added) e m

i a

e

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT.....................

6-19 6.14 10D I fj E MON I TO R I N G............................................ 6-2 0 6.15 ENVIRONitENTAL QUALIFICATION..................................

6-21 HATCH-UNIT 2 XVII Amendment No.18 e

INSTRUMENTATION POST-ACCIDENT MONITORING INSTRUMENTATION _

j LIMITING CONDITION FOR OPERATION t

3.3.6.4 The post-accident monitoring instrumentation channels shown in Table 3.3.6.4-1 shall be OPERABLE.

APPLICABILITY: CONDITIONS 1 and 2.

ACTION:

l With one or more of the above required post-accident monitoring a.

channels inoperable, either restore the inoperable channel (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

The provisions of Specification 3.0.4 are not applicable.

I I,

SURVEILLANCE REQUIREMENTS 4.3.6.4 Each of the above required post-accident monitoring instrumen-tation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.6.4-1.

i i

a HATCH - UNIT 2 3/4 3-53 1

TABLE 3.3.6.4-1 POST-ACCIDENT MONITORING INSTRUMENTATION m

E MINIMUM g

CHANNELS h

INSTRUMENT OPERABLE O

1.

Reactor Vessel Pressure (2C32-R605 A, B, C) 2 E

E 2.

Reactor Vessel Water Level (2B21-R610, 2B21-R615) 2 n

3.

Suppression Chamber Water Level (2T48-R622 A, B) 2 4.

Suppression Chamber Water Temperature (2T47-R626, 2T47-R627) 2 5.

Suppression Chamber Pressure (2T48-R608,2T48-R609) 2 2

6.

Drywell Pressure (2T48-R608, 2T48-R609)

$d 7.

Drywell Temperature (2T47-R626, 2T47-R627) 2 w

y 8.

Post-LOCA Gamma Radiation (2Dll-K622 A, B, C, D) 2 9.

Drywell H

-0 Analyzer (2P33-R601 A, B) 2 2

2 10.a) Safety / Relief Valve Position Primary Indicator (2B21-N301 A-H and K-M) b) Safety / Relief Valve Position Secondary Indicator (2B21-N004 A-H and K-M) 8

If either the primary or secondary indication is inoperable, the torus temperature will be menitored R

at least once per shif t to observe any unexplained temperature increases which might be indicative s

of an open SRV. With both the primary and secondary monitoring channels of two or more SRVs inoperable 5

either restore sufficient inoperable channels such that no more than one SRV has both primary and secondary channels inoperable within 7 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

=

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TABLE 4.3.6.4-1 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

CHANNEL CHANNEL INSTRUMENT CllECK CALIBRATION

~

Ey 1.

Reactor Vessel Pressure M

Q w

2.

Reactor Vessel Water Level M

Q 3.

Suppression Chamber Water Level M

R M

R 4.

Suppression Chamber Watcr Temperature M

R 5.

Suppression Chamber Pressure t

M Q

{

6.

Drywell Pressure M

R

[

7.

Dryvall Temperature w

8.

Post-LOCA Gamma Radiation M

R M

Q 9.

Drywell H2 -02 Analyzer 10.

a) Safety / Relief Valve Position Primary Indication M*

R b) Safety / Relief Valve Position Secondary Indication M*

R F

a o.

See 4.4.2.a emed N

INSTRUMENTATION SOURCE RANGE MONITORS _

LIMITING CONDITION FOR OPERATION _

3.3.6.5 Three source range monitors shall be OPERABLE.

APPLICABILITY: CONDITIONS 2*, 3 and 4.

ACTION:

In CONDITION 2* with one of the above required source range monitors a.

inoperable, restore 3 source range monitors to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

In CONDITION 3 or 4, with two or more of the above required source range monitors inoperable, verify all control rods to be fully insertec in the core and lock the reactor mode switch in the Shutdown position within one hour.

SURVEILLANCE REQUIREMLNTS 4.3.6.5 Each of the above required source range monitors shall be demon-strated OPERABLE by:

a.

Performance of a:

1.

CHANNEL CHECK at least once per.

(a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in CONDITION 2*, and (b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in CONDITION 3 or 4.

2.

CHANNEL CALIBRATION ** at least once per 18 months.

b.

Performance of a CHANNEL FUNCTI0t AL TEST:

1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to moving the reactor mode switch from the Shutdown position if not performed within the previous 7 days, and 2.

At least once per 31 days.

Verifying, prior to withdrawal of control rods, that the SRM count c.

rate is at least 3 cps witn the detector fully inserted.

With IRMs on range 2 or below.

- May exclude neutron detectors.

HATCH-UNIT 2 3/4 3-56

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tianager will obtain a Senior Reactor Operator's Lines of Responsibility License.

....-_. ____.----- I.Inen of Communication Figure 6.2.2-1 UNIT ORGANIZATION

TABLE 6.2.2-1 MINIMIM SHIFT CREW COMPOSITION #

Condition of Unit 2 - Unit 1 in Reactor Power Operation, llot Standby or liot Shutdown Condition LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOD

2 2*

OL**

3 2

Non-Licensed 3

3 Shift Technical Advisor 1

1 Condition of Unit 2 - Unit 1 in Cold Shutdown Condition or Refuel Mode LICENSE APPLICABLE CATECORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL **

2 1*

OL**

2 2

Non-Licensed 3

3 Shift Technical Advisor 1

None Condition of Unit 2 - No Fuel in Unit i LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 S0J.

I 1*

OJ.

2 1

Non-Licensed 2

1 Shift Technical Advisor 1

None

Does not include the Licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel llandling, supervising CORK ALTERATIONS.

A mume, each individual is licensed on both units.

Shift crew composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew members provided immediate nction is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.2-1.

PLANT HATCH UNIT 2 6-4

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATICNS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the llealth Physicist-Radiochemist who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor *who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, t

and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Senior Methods and Training Specialist and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for fire protection shall be maintained under the direction of the Senior Regulatory Specialist and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for fire protection training sessions which shall be held at 1 cast once per 92 days.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB1 Fpi;CTION 6.5.1.1 The PRB shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review Board shall be composed of the:

Chairmsa:

Plant Manager Vice Chairman:

Assistant Plant Manager Member:

Operations Superintendent Member:

Superintendent Plant Engineer Services Member:

thintenance Superintendent Member:

Senior Quality Control Specialist Member:

llealth Physicist-Radiochemist ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PRB activities at any one time.

The qualifications for the Shif t Technical Advisor apply af ter January 1,1981.

Amendment No.18 PLANT !! ATCll UNIT 2 6-5

ADMINI,lRATIVL LONTROIL MEETING FREQUENCY 6.5.1.4 The PR8 shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate.

_QUORtiM 6.5.1.5 The minimum quorum of the PRC necessary for the performance cf the PRB responsibility and luthority provisions of these Technical Specifications shall consist of the Chairman or Vice Chairman and three members including alternates.

RESPONSIBILITIFS 6.5.1.6 The Plant Review Board shal! be responsible for a.

Review of (l' al1 F ocedaru e.,.. i r s d L.

S pt..iticetico 6.8 and cfinge; therete, (2) any of.hc r prcposed proctJures or changes thereto as detern.ined by the Plant Manager to affect nuclear safety.

b.

Review of all propose ( test <. and experiments that affect nuclear safety.

Review of all proposed changes to Appendix "A" Technical c.

Specifications.

d.

Review of all proposed changes or modifications to unit system:. or equipment that affect nuclear safety.

Inves tigation of all violations of the Technical Specifications e.

including the preparation and forwarding of reports covering evaluation and reconnendations to prevent recurrence to the Manager of Production and to the Safety Review Board (SRB).

f.

Review of events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification to the Conmission.

Review of unit operations to detect potcnt',1 nuclear 9

safet, hazards.

h.

Performance of special reviews, inves tigations or analyses and reports thereon as requested by the Plant Manager or r Of; the HATCH - Oh!T 2 6- 0

ADMINISTRAT HE CONTROL 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 radi tion monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received.

Entry into such areas wi'1 this monitcring device may be made after the dose rate 'evel in the area has been established and personnel have been made knowl-edgeable 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 Physicist in the Radiation Work Permit.

5.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater shan 1000 mrem /hr In addition, locked doors shall be provided to prevent anautherized entry into such areas ar,d the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or tne Plant Health Physicist.

6.13 INTEGRITY OF SYSTEMS OUTSIDE CON 1AINiiEll_T lcontainnent that would or could contain highly radioactive fluids during a ihe licensee shall implement a progran to reduce leakage from systems outside l

j serious transient or accident to as low as practical levels.

This program shall include the following:

1)

Provisions establishing preventive maintenance and periodic visual inspec-tion requirements, and

2) System leak test requirements, to t he 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 Renoval, (2) Core Spray, (3) Reactor Water Cleanup, (4)

HPCI, and (6) RCIC.

HAICH-UNIT 2 6-19 Anendnent No. 13

Al)MINISTRATIVE CONTROL

_ ~J 6.14 IODINE I40NITORING The licensee shall implenent a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

under accident conditions. This progran shall include the following:

1)

Training of personnel,

2)

Procedures for monitoring, and 3)

Provisions for maintenance of sampling and analysis equipnent.

t Areas requiring personnel access for establishing hot shutdown condition.

i i

HATCH-UNIT 2 6-20 Amendnent No.18

ML19340C223

Text

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