Text

Proposed Tech Specs,Incorporating Revised Reporting Requirements of 10CFR50.72 & 50.73 on Primary Coolant Iodine Spikes
	ML20212H439
Person / Time
Site:	Hatch
Issue date:	02/13/1987
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20212H416	List: ML20212H413; ML20212H439;
References
	GL-83-43, TAC-55713, TAC-55714, NUDOCS 8703060106
	Download: ML20212H439 (52)
	v • d • e

Section Page Section LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.14 RADIOACTIVE EFFLU;NT 3.14 RADIOACTIVE EFFLUENT INSTRUMENTATION INSTRUMENTATION 3.15 RADIDACTIVE EFFLUENT 4.15 RADIDAC11VE EFFLUENT CONCENTRATION AND DOSE CONCENTRATION AND DOSE 3.16 ENVIRONMENTAL 4.16 ENVIRONMENTAL MONITORING PROGRAM MONITORING PROGRAM 5.0 MAJOR DESIGN FEATURES 5. 0-1 A. Site 5. 0-1

8. Reactor Core 5.0-1 C. Reactor Vessel 5. 0-1

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0. Containment 5. 0-1 E. Fuel Storage 5.0-1 F. Seismic Design 5.0-2 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Unit Staff Qualifications 6-6 6.4 Training 6-6 6.5 Review and Audit 6-6 6.6 Reportable Event Action 6-13 l 6.7 Safety Limit Violation 6-13 6.8 Procedures 6-14 6.g Reporting Requirements 6-15 6.10 Record Retention 6-23 6.11 Radiation Protection Program 6-25 6.12 High Radiation Area 6-25 1

6.13 Integrity of Systems Outside Containment

6-26 6.14 lodine Monitoring 6-27 6.15 Post Accident Sampling and Analysis 6-27 6.16 Offsite Oose Calculation Manual 6-27 f

i 0703060106 D70213 DR ADOCK 0500 1 HATCH - UNIT 1 vi Proposed TS/0046q/8401-1

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i 1.0 OEFINITIONS (Continued)

EEE. MILK ANIMAL A cow or goat that is producing milk for human consumption.

4 FFF. DOSE EQUIVALENT IODINE The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram), which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133,1-134, and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in table III of TID-14844 or those in NRC Regulatory Guide 1.109, Revision 1, October 1977.

666. ACTign ACTION shall be that part of a specification which prescribes remedial measures required under daignated conditions.

HHH. CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

III. REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. -

i HATCH - UNIT 1 1.0-10 Proposed TS/00474/8401-1

LIMITING CONDITIONS FOR OPERATION ShRVEILLANCE REQUIREMENTS 3.6.F. Reactor Coolant Chemistry 4.6.F. Reactor Coolant Chemistry

1. Radioactivity 1. Radioactivity Whenever the reactor is critical a. During equilibrium power the limits on activity concen- operation an isotopic trations in the reactor coolant analysis, including shall not exceed the equilibrium quantitative measurements value of 0.2 pCi/gm of dose f or at least I-131,1-132, equivalent

1-131. 1-133, and I-135 shall be performed monthly on a coolant liquid sample,

b. During equilibrium power operation an isotopic analysis, including quantitative measurements for at least Xe-133 and Xe-135 shall be perfonned monthly on a steam jet air ejector of f-gas sample,

c. Additional coolant samples shall be taken whenever the reactor coolant dose equiva-1ent I-131 concentration exceeds 0.2 w C1/gm and any of the following conditions if activity concentration >0.2 are met:

y C1/gm dose equivalent 1-131 but

< 4.0 v C1/gm for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 1) During startup during one continuous time interval, or >4.0 v C1/ge, be in at least 2) Following a power change NOT SHUTDOWN with the main steam line exceeding 15% of rated isolation valves closed within 12 thermal power in less hours. than I hour (net change averaged for I hour).

That 1-131 concentration which alone would 3) The off-gas level, at produce the same thyroid dose as the the SJAE, increases by quantity and todine mixture actually more than 10,000 pC1/sec present, in I hour at release rate 5,15,000 pC1/sec, or

4) The off-gas level at the SJAE,, increases by more than 155 in I hour at release rate > 75,000 wC1/sec.

5) Whenever the reactor coolant dose equivalent 1-13) concentration ex-ceeds 4.0 pC1/ge.

HATCH ,- UNii 1 3. 6-4 Proposed 75/0048q/8401-1

LIMITING CON 0lil0NS FOR OPERATION SURVEILLANCE REQUIREMENTS The first add 1'tional

. Coolant sample shall be taken between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following the change in thernal power or of f-gas level. Additional coolant 11guld samples shall be taken at 4-hour iatervals for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or until a stable iodine concentra-tion below the limiting value of 4.0 vC1/gm is established. An isotopic analysis shall be performed for each sample, and quantitative measurements made to determine the dose equivalent I-131 concen-tration. If the total iodine activity of the sample is below 0.2 vC1/ge, an isotopic analysis to determine equivalent 1-131 is not required.

All data obtained from normal and any additional samples shall be included in the annual report.

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I HATCH - UNif 1 3.6-5 Proposed TS/0048q/8401-1

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.6.H.1. Relief / Safety Valves 4.6.H.1. Relief / Safety Valves

a. When one or more relief / safety a. End of Operatino Cvele valve (s) is known to be failed ** an orderly shutdown shall be initiated Approximately one-half of all and the reactor depressurized to relief / safety valves shall be less than 113 psig within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . benchchecked or replaced with Prior to reactor startup f rom a a benchchecked valve each re-cold condition all relief / safety fueling outage. All 11 valves valves shall be operable. will have been checked or re-placed upon the completion of every second operating cycle.

b. With one or more relief / safety b. Each Operatina Cycit valve (s) stuck open, place the reactor mode switch in the shutdown position. Once during each operating cycle, at a reactor pressure

> 100 psig each relief valve shall be manually opened until thermocouples downstream of the valve indicate steam is flow-ing from the valve.

c. With one or more safety / relief valve c. Inteority of Relief Valve tallpipe pressure switches of a g_e,l e l ows

safety / relief va he declared inoperable and the associated The integrity of the relief valve safety / relief valve (s) otherwise bellows shall be continuously indicated to be cpen, place the monitor J and the pressure reactor mode switch in the Shut- switch calibrated once per down position, operating cycle and the accu-mulators and air piping shall be inspected for leakage once per operating cycle,

d. With one safety / relief valve tailpipe d. Relief Valve Maintenance pressure switch of a safety / relief valve declared inoperable and the asso- At least one relief valve shall ciated safety / relief valve (s) otherwise be disassembled and inspected indicated to be closed, plant operation each operating cycle.

may continue. Remove the function of that pressure switch from the low low e. Qperability of Tail Pioe set logic circuitry until the next COLO Pressure Switches SHUTOOWN. Upon COLD SHUTOOWN, restore the pressure switch (es) to OPERABLE The tail pipe pressure switch status before STARTUP. of each reIIef/ safety valve shall be demonstrated operable

e. With both safety / relief valve ta11 pipe by perfoi nance of a:

pressure switches of a safety / relief valve declared inoperable and the asso- 1. Functional Test:

clated safety / relief valve (s) otherwise indicated to be closed, restore at least a. At least once per 31 one inoperable switch to OPERABLE status days, except that all within 14 days or be in at least HOT portions of instrumen-SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months tation inside the pri-and in COLD SHUTOOWN within the mary containment may be following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , escluded from the functional test, and

0oes not apply to two-stage Target Rock $RVs

- The failure or malfunction of any safety / relief valve shall be reported by telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; confirmed by telegraph, mallgram, or f acsimile transmission to the 01 rector of the Regional Office or his designee no later than the first working day following the event; and a written follow-up report within 30 days. The written follow-up report should be completed in accordance with 10 CFR 50.73 or other appilcable requirements.

HATCH - UNIT I 3.6-9 Proposed TS/004HQ/8401-1

LINITING CON 0lil0NS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A.2.e. Tvoo B Tes';s - Leak Tests of Sea' s and Penetrations (Table 3.7-2 and 3.7-3)

(Continued).

(2) (a) The personnel air lock shall be tested at in-tervals not to exceed six months at Pa by pres-surizing the compartment between the two air lock doors.

During intervals of door use when containment integrity is required, I the door seals shall be tested at 10 psig af ter each opening, (b) Personnel air lock leakage shall not exceed 0.05 La.

f. Tvoe C Tests-Local Lenk Tests of Contatnment isolat' on valves (Tables 3.7-1 and 3.7-4)

Type C tests shall be performed under the program established in Appendix J of 10 CFR Part 50.

Containment isolation valves (except for main steam line iso-lation valves) shall be tested at a pressure not less than P a*

Type C tests shall be performed at each major refueling shutdown or at intervals not to exceed two years.* l

A11 Type 8 and Type C Leakage Tests (i.e., Local Leak Rate Tests) that fall (i.e., test leakage is such that an LER would be required) during an outage shaII be reported according to 10 CFR 50.73 by one, 30-day written report that is due within 30 days of the first leakage test failure in the outage.

All other leakage test failures discovered during the outage will be reported in a revision to the original report due within 30 days af ter the end of the outage.

HATCH - UNIT 1 3.7-6 Proposed T5/00494/0401-1

LIMITING CONDITIONS FOR OPE 4AT10N SURVEILLANCE REQUIREMENTS

g. Acceptance Criteria for Twee 8 and Twee C Tests The combined leakage rate of components subject to Type 8 and C tests shall be determined under the program established in Appendix J of 10 CFR Part 50 ,

and shall not exceed 0.6 La .'

h. Main Steam Line Isolation Valves The main steam line isola-tion valves shall be tested at a pressure of 1/2 Pa for leakage at least once per operating cycle. If a total leak rate of 11.5 scf per hour for any one main steam line isolation valve is .

exceeded, repairs and retest shall be performed to correct this condition.

All Type 8 and Type C Leakage Tests (i.e., Local Leak Rate Tests) that fail (i.e., test leakage is such that an LER would be required) during an outage shall be reported according to 10 CFR 50.13 by one, 30 day written report that is due within 30 days of the first leakage test failure in the outage.

All other leakage test failures discovered during the outage will be reported in a revision to the original report due within 30 days af ter the end of the outage.

J HATCH - UNIT I 3.7-6a Proposed TS/0049q/8401-1

LIMitlNG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11. C . Minimum Critical Power Ratio (MCPR)

(Continued) n I Ni ti

-i tave = 1"I n

l INi i=1 n = number of surveillance tests performed to date in cycle Nj = number of active control rods measured in the ith surve111ance test 51 - Average scram time to 205 in-sortion from fully withdrawn of all rods measured in the ith surveillance test, and, N1 = total number of active rods measured in 4.3.C.2.a.

If at any time during operation it is determined by normal surveillance that the limiting value for MCPR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. If the steady state MCPR is not returned to within the prescribed limits within two (2) hours, then reduce reactor power to 4 less than 2$5 of rated thermal power within the next four(4) hours. If the Limiting Condition for Operation i is restored prior to emptration of i the specified time laterval, then further progression to less than 25% of rated thermal power is not required. *

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HATCH - UNIT 1 3.11-24 Proposed T5/0050q/8401-1

BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3.11.C. Minimum Critical Power Ratio (MCPR) (Continued)

At core thermal power levels less than or equal to 255, the reactor will be operating at minimum recirculation pump speed and the moderator void content will be very small. For all designated control rod patterns which may be en-ployed at this point, operating plant experience and thermal hydraulic analy-sis indicated that the resulting MCPR value is in excess of requirements by a considerable margin. With this low void content, any inadvertent core flow increase would only place operation in a more conservative mode relative to

! MCPR. During initial start-up testing of the plant, a MCPR evaluation will be made at the 255 thermal power level with minimum recirculation pump speed.

The MCPR margin will thus be demonstrated such that future MCPR evaluations below this power level will be shown to be unnecessary. The daily require-ment for calculating MCPR above 255 rated thermal power is sufficient since power distribution shif ts are very slow when there have not been significant power or control . rod changes. The requirement for calculating MCPR when a limiting control rod pattern is approached ensures that MCPR will be known following a change in power or power shape (regardless of magnitude) that could place operation'at a thermal limit.

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HATCH - UNIT 1 3.11-5 Proposed TS/0050q/8401-1 l

ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4. The PR8 shall meet at least once per calendar month and as convened by the PR8 Chairman or his designated alternate.

OUORUM 6.5.1.5. The minimum quorum of the PR8 necessary for the performance of the PRO responsibility and authority provisions of these Technical Specificatians shall consist of the Chairman or Vice Chairman and four voting members including alternates.

RESPONSI81LITIES 6.5.1.6. The Plant Review Board shall be responsible for:

a. Review of (1) all procedures required by Specification 6.8. and changes thereto. (2) any other proposed procedures or changes thereto as determined by the General Manager-Plant Hatch to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Appendix 'A' Technical Specifications.

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering i

evaluation and recommendations to prevent recurrence to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations and to the Safety Review Board (SR8).

f. Review of all REPORTA8LE EVENTS.

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g. Review of unit operations to detect potential nuclear safety hazards.

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Ger.eral Manager-Plant Hatch or the SRO. '

HATCH - UNIT 1 6-7 Proposed TS/0052q/8401-1 1

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ADMINISTRATIVE CONTROLS QUORUN 6.5.2.6. The minimum quorum of the SRB necessary for the performance of the SRB review and audit functions of these Technical Specifications shall consist of the Chairman or Vice Chairman and at least 3 SR8 members. No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW 6.5.2.7. The SRO shall review:

a. The safety evaluations for (1) changes to procedures, equipment or systems and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes to Technical Specifications or this Operating License.

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e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

g. All REPORTA8LE EVENTS. l

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

1. Reports and meetings minutes of the Plant Review Board. ,

HATCH - UNIT 1 6-10 Proposed TS/0052q/8401-1

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ADMINISTRATIVE CONTROLS

k. The Radiological Environmental Monitoring Program and the results thereof annually.

1. The 00CM, PCP, and implementing procedures biennially.

AUTHORITY 6.5.2.9. The SR8 shall report to and advise the Executive Vice President -

Power Supply on those areas of responsibility specified in Sections 6.5.2.7.

and 6.5.2.8.

RECOROS 6.5.2.10. Records of SRB activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each SRB meeting shall be prepared, approved and forwarded to the Executive Vice President-Power Supply within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7. above, shall be prepared, approved and forwarded to the Executive Vice President-Pover Supply within 14 days following completion of the review.

c. Audit reports encompassed by Section 6.5.2.8. above, shall be forwarded to the Executive Vice President-Power Supply and to the nunagement positions responsible for the areas audited within 30 days af ter completion of the audit.

6.6. REPORTA8LE EVENT ACTION 6.6.1. The following actions shall be taken for REPORTA8LE EVENTS:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTA8LE EVENT shall be reviewed by the PR8 and the results of this review shall be submitted to the SRB and the Manager of Nuclear Generation or the Vice President and General Manager

Nuclear Opt rations.

6.7. SAFETY LIMIT VIOLATION 6.7.1. The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT SHUTOOWN within two hours,

b. The Safety Limit violation shall be reported to the Commission as soon as practical and in all cases within one hour of occurrence.

The Manager Nuclear Generation or the Vice President and General Manager Nuclear Operations and the SRB shall be notified within 24 l hours.

I HATCH - UNIT 1 6-12 Proposed TS/0052q/8401-1 l

4 ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

c. A Licensee Event Report shall be prepared pursuant to 10CFR50.73.

d. The Licensee Event Report shall be submitted to the Commission in accordance with 10CFR50.73, and to the PRB, the SRB, and the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations within 30 days of the violation. l 6.8. PROCEDURES 6.8.1. Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix 'A' of Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

4 6.5.2 Each procedure of 6.8.1. and other procedures which the General Manager - Plant Hatch has determined to af fect nuclear safety, and changes thereto, shall be reviewed by the PR8 and approved by the appropriate member of plant management, designated by the General Manager - Plant Hatch, prior to implementation. The General Manager - Plant Hatch will approve administrative procedures, security plan implementing procedures, emergency plan implementing procedures and changes thereto. All other procedures of this specification and changes thereto will be approved by the department head designated by the General Manager - Plant Hatch. The procedures of this specification shall be reviewed periodically as set forth in administrative procedures. .

6.8.3. Temporary changes to procedures of 6.8.1. above may be made provided:

a. The intent of the original procedure is not altered.

HATCH - UNIT 1 6-13 Proposed TS/00744/8401-1

ADNINISTRATIVE CONTROLS ,

6.9. REPORTING REQUIRENENTS ROUTINE REPORTS l 6.9.1. In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1. A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2. The startup report shall address each of the tests identified in the FSAA and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.

6.9.1.3. Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption l'

or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of connercial operation), supplementary reports shall be submitted at least every three months until all three events have bean completed.

l ANNUALREPORTSd l

6.9.1.4. Annual reports covering the activities of the unit as described I below for the previous calendar year shall be submitted prior to March 1 l of each year. The initial report shall be submitted prior to March 1 of i the year following initial criticality.

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F A single submittal may be made for a multiple unit station. The l submittal should combine those sections that are common to all units at the station.

HATCM - UNIT 1 6-14 Proposed TS/0052qd401-1 i

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AONINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) 6.9.1.5. Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel, including contractors, receiving exposures greater than 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 (describe maintenance), waste processing, and ref uell..g. The dose assignment to various duty functions may be

estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 205 of the individual total dose need not be accounted for. In the aggregate, at least 805 of the total whole body dose received from external sources shall be assigned to specific major work functions.

b. Documentation of all challenges to safety / relief valves, t

c. The results of specific activity analysis in which the primary j coolant exceeded the limits of Specification 3.6.F.1. The j

following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result j should include date and time of sampling and the radiciodine i

concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

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d. Any other unit unique reports required on an annual basis. l l

ANNUAL RADIOLOGICAL ENVIRONNENTAL SURVEILLANCE REPORT (a) 6.g.1.6 Routine radiological environmental surveillance reports covering the radielegical eevironmental surveillance activities related to the plant during the previous calendar year shall be submitted prior to May 1 of each year. A single report may fulfill this requirement for both unitse l

6.g.1.7 The Annual Radiological Environmental Surveillance Report shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the reporting period, including (as appropriate) a comparison with the preoperational studies, operational controls, previous environmental j surveillance reports, and an assessment of any observed impacts of the j plant operation on the environment. The reports shall also include the i

a. A single submittal may be made for a multiple-unit station. The submittal should combine those sections conson to all units at the station.

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This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

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l HATCH - UNIT 1 6-15 Proposed TS/00524/8401-1

TA8LE 6.9.1.7-1 x ENVIR00lMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

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Iteme of Facility Edwin 1. Hatch Nuclear Plant Docket No. 50-321, 50-366 e Location of Facliity Appline County. Georela Reporting Period C

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>< Location of H Highest Annual Mean

- w Medium or Type and Pathway Sampled Total Number Lower Limit All Indicator Name, Control Numbe r of (Unit of of Analyses of Locations Distance, Mean Locations REPORTABLE Measurement) Performed Detection'*8 Mean Range and Direction Range Mean Range EVENTS l 1

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a. Lower Limit of Detection is defined in table notation a of table 4.16.1-1, Specification 4.16.1. of Unit 1.

o b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is

, *;* Indicated in parentheses.

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ADMINISTRATIVE CONTROLS

e. Type of container, e.g., LSA, type A, type 8, large quantity,

f. Solidification agent, e.g., cement.

The Radioactive Effluent Release Report shall include (on a quarterly basis) unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents that were in excess of I Ci, excluding dissolved and entrained gases and tritium for liquid cffluents, or those in excess of 150 Ci of noble gases or 0.02 C1 of radiciodines for gaseous releases.-

The Radioactive Effluent Release Report shall include any changes to the PROCESS CONTROL PRO 6 RAM and to the OFFSITE DOSE CALCULATION MANUAL made during the reporting period.

MONTHLY OPERATING REPORT l 6.g.1.10. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director Office of Management and Program Analysis, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the Regional Office of Inspection and Enforcement no later than the 15th of each month following the calendar month covered by the report.

i HATCH - UNIT 1 6-15d Proposed TS/00524/8401-1 ,

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E HATCH - UNIT 1 6-16 Proposed TS/00524/8401-1

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HATCH - UNIT 1 6-17 Proposed TS/0052q/8401-1 1

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ADMINISTRATIVE CONTROLS SPECIAL REPORT 1 6.9.2. Special reports shall be submitted to the Director of the Of fice of Inspection and Enforcement Regional Office within the time period specified and for each activity shown in Table 6.9.2-1. Special reports for fire protection equipment operating and surveillance requirements shall be submitted, as required, by the Fire Hazards Analysis and its Appendix 8 requirements.

6.10. RECORD RETENTION In addition to the applicable record retention requirements of Title'10 Code of Federal Regulations, the following records shall be retained for

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at least the minimum period indicated.

6.10.1. The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level,

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. ALL REPORTABLE EVENTS submitted to the Commission. l

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments,

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

6.10.2. The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modifi-cations made to systems and equipment described in the Final Safety Analysis Roport.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

HATCH - UNIT 1 6-18 Proposed TS/00524/8401-1

f l

t 4.0 Special Surve111ance and Study Activities 4.1 Erosion Control Inspection 4.2 Unusual or Important Events Reautrements Requirements The licensee shall be alert to the occurrence of unusual or important events. Unusual or important events are those that -

cause potentially significant environmental impact, or could be i of pubite interest concerning environmental impact from plant -

operation. The following are examples: unusual or important bird impaction events on cooling tower structures or meteorological towers, onsite plant or animal disease outbreaks, unusual mortality of any species protected by the Endangered Species Act of 1973, fish kills near the HNP site, and significant violations of relevant permits and certifications. :

Action .

Should an unusual or important event occur, the licensee shall make a report to the NRC as required by 10 CFR 50.72 or 10 CFR 50.73.

Bases Prompt reporting to the NRC of unusual or important events, as described, is necessary for responsible and orderly regulation I of the nation's system of nuclear power reactors. The information thus provided may be useful or necessary to others concerned with the same environmental resources. Prompt knowledge and action may serve to alleviate the magnitude of environmental impact or to place it into a perspective broader than that available to the licensee. The NRC also has an obligation to be responsible to inquiries from the pubite and the l news media concerning potentially significant environmental events at nuclear power stations. l 4.3 Exceedine Limits of Other Relevant Permits Requirements ,

i The ifcensee shall notify the NRC of occurrences exceeding the i Ilmits specified in relevant permits and certificates issued by

other Federal, State, and local agencies that are reportable to tt. agency that issued the permit. This requirement shall apply

only to topics of NEPA concern within the NRC area of j responsibility as identified in the Environmental Technical l

Specifications (ETS). ,

i l

HATCH - UNIT 1 4-1 Proposed TS/0056q/8401-1

,This requirement shall commence with the date of issuance of the operating license *for Unit 2 and continue until approval for modification or termination is obtained from the NRC in accordance with section 5.6.3.

Action The licensee shall make a report to the NRC in the event of a REPORTABLE EVENT exceeding a limit specified in a relevant permit or certificate issued by another Federal, State, or local agency. The report shall be submitted within the time limit specified by the reporting requirement of the corresponding certification or permit issued pursuant to Section 401 or 402 of PL 92-500. The report will consist of a copy of the report made to the Georgia Department of Natural Resources, Environmental Protection Division.

Bases The NRC is required under NEPA to maintain an awareness of environmental impacts causally related to the construction and operation of facilities licensed under its authority. Further, some of the ETS requirements are couched in terms of compliance with relevant permits, e.g., the NPDES permit, issued by other licensing authorities. The reports of exceeding limits of relevant permits also alert the NRC staff to environmental problems that may require mitigative action.

HATCH - UNIT 1 4-2 Proposed TS/0056q/8401-1

5.6.2 Nonroutine Reports ,

(Deleted. Refer to 10 CFR 50.72 and 10 CFR 50.73 for reporting requirements.)

5.6.3 Changes in Environmental Technical Specifications

and Permits 5.6.3.1 Channes in Environmental Technical Specifications Requests for changes in ETS shall be submitted to the NRC for ;

review and authorization in accordance with 10 CFR 50.90. The request shall include an evaluation of the environmental impact of the proposed change and a supporting justification.

Implementation of such requested changes in ETS shall not commence prior to incorporation by the NRC of the new specifications in the license.

1 HATCH - UNIT 1 5-8 Proposed TS/0053q/8401-1

INDEX OEFINITIONS SECTION T

1.0 DEFINITIONS (Continued) PAGE REPORTA8LE EVENT 1-9 TABLE 1.1, SURVEILLANCE FREQUENCY NOTATION 1-10 TABLE 1.2, OPERATIONAL CONDITIONS 1-11 1

a 1

f i

I

HATCH-UNIT 2 iia Proposed TS/0054q/8402-1

INDEX

~

ADMINISTRATIVE CONTROLS SECTION PAGE SAFETY REVIEW BOARD (Continued)

Audits 6-10 Authority 6-11 Records 6-11 6.6 REPORTA8LE EVENT ACTION 6-11 l 6.7 SAFETY LIMIT VIOLATION 6-11 6.8 PROCEDURES 6-12 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6-13 l STARTUP REPORT 6-13 ANNUAL REPORTS 6-13 ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT 6-14 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6-14a MONTHLY OPERATING REPORT 6-14d t'

5PECIAL REPORTS 6-17 6.10 RECORD RETENTION 6-17 6.11 RADIATION PROTECTION PROGRAM 6-18 6.12 HIGH RADIATION AREA 6-18 HATCH-UNIT 2 XVI Proposed TS/0054q/8402-1

1.0 DEFINITIONS (Continued)

VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required during VENTING. The term " vent" used in system names does not imply a VENTING process.

MILK ANIMAL A cow or goat that is producing milk for human consumption.

REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

i NATCN - UNIT 2 1-9 Proposed TS/0055q/8402-1 r

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION j

3.3.6.2 The seismic monitoring instrumentation shown in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITY: At all times.

, ACTION:

l

a. With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, in lieu of any other report required by 10 CFR 50.73, prepare and submit l a Special Report to the Commission within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.6.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, l

CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the fre-i quencies shown in Table 4.3.6.2-1.

4.3.6.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 30 days following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. In lieu of any other report raquired by 10 CFR 50.73, ~ l '

2 a Special Report shall be prepared and submitted to the Com-mission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.

1 i

i HATCH - UNIT 2 3/4 3-47 Proposed TS/0057q/8402-1

REACTOR COOLANT SYSTEN 3/4.4.2 SAFETY / RELIEF VALVES LINITING CONDITION FOR OPERATION 3.4.2.1 The safety valve function of the following reactor coolant system safety / relief valves shall be OPERABLE with the mechanical lift settings within i 1% of the indicated pressures *.

4 Safety-relief valves 4 1090 psig.

4 Safety-relief valves 9 1100 psig**.

3 Safety-relief valves 0 1110 psig**.

APPLICABILITY: CONDITIONS 1, 2 and 3.

ACTION:

a. For low-low set valves, take the action required by Specification 3.4.2.2. For ADS valves, take the action required by Specification 3.5.2.

b. With one or more safety / relief valves stuck open, place the reactor mode switch in the Shutdown position.

c. With one or more S/RV tailpipe pressure switches of an S/RV declared inoperable and the associated S/RV(s) otherwise indicated to be open, place the reactor mode switch in the shutdown position.

d. With one S/RV tailpipe pressure switch of an S/RV declared inoperable and the associated S/RV(s) otherwise indicated to be closed, plant operation may continue. Remove the function of that pressure switch from the low low set logic circuitry until the next COLD SHUTDOWN.

Upon COLD SHUTOOWN, restore the pressure switch (s) to OPERABLE status before STARTUP.

e. With both S/RV tailpipe pressure switches of an S/RV declared inop-erable and the associated S/RV(s) otherwise indicated to be closed, restore at least one inoperable switch to OPERABLE status within 14 days or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLO SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

f. The failure or malfunction of any safety / relief valve shall be reported by telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designee no later than the first working day following the event; and a written followup report within 30 days.

The written followup report should be completed in accordance with 10 CFR 50.73 or other applicable requirements.

SURVEILLANCE REOUIRENENTS 4.4.2.1 The tail-pipe pressure switches of each safety / relief valve shall be demonstrated OPERABLE by performance of:

a. CHANNEL FUNCTIONAL TEST:

1. At least once per 31 days, except that all portions of the channel inside the primary containment may be excluded from the CHANNEL FUNCTIONAL TEST, and

2. At each scheduled outage of greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during which entry is made into the primary containment, if not performed within the previous 31 days,

b. CHANNEL CALIBRATION and verifying the setpoint to be 85 psig, with an allowable tolerance of +15 psig and -5 psig, at least once per 18 months,

The lif t setting pressure shall correspond to ambient conditions of the valves at nominal operating temperature and pressure.

- Up to two inoperable valves may be replaced with spare OPERABLE valves with lower setpoirts of 1090 and 1100 psig, respectively, until the next refueling outage.

HATCH - UNIT 2 3/4 4-4 Proposed TS/0060g/8402-1

REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICA8ILITY: At all times.

ACTION:

a. In CONDITION 1, 2 and 3:

1. With the conductivity or chloride concentration exceeding the limit specified in Table 3.4.4-1, but less than 10 pmho/cm at 25'C and less than 0.5 ppm, respectively, operation may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and this need not be reported to the Commission, provided that operation under these conditions !

shall not exceed 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year. If operation under these conditions exceeds 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, in lieu of any other report required by 10 CFR 50.73, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2, within 30 days, outlining the course of the limit violation and the plans for restoring the conductivity or chloride concentration to within the limit. The provisions of Specification 3.0.4 are not applicable.

2. With the conductivity or chloride concentration exceeding the limit specified in Table 3.4.4-1 for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during one continuous time interval or with the conductivity exceeding 10 pmho/cm at 25'C or chloride exceeding 0.5 ppm, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. At all other times:

1. With the conductivity of the reactor coolant in excess of the limit specified in Table 3.4.4-1, restore the conductivity to within the limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. With the chloride limit of Table 3.4.4-1 exceeded for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system. Determine that the structural integrity of the reactor coolint system remains acceptable for continued operation prior to proceeding to CONDITION 3.

HATCH - UNIT 2 3/4 4-7 Proposed TS/0060g/8402-1

)

l 1

REACTOR COOLANT SYSTEM i 3/4.4.5 SPECIFIC ACTIVITY LINITING CONDITION FOR OPERATION 1

3.4.5 The specific activity of the reactor coolant shall be limited to:

a. 5 0.2 pCi/ gram DOSE EQUIVALENT I-131, and

b. 5 100/E wC1/ gram.

APPLICA81LITY: CONDITIONS 1, 2, 3 and 4.

ETig:

a. In CONDITIONS 1, 2 and 3, with the specific activity of the reactor coolant;

1. > 0.2 vCi/ gram DOSE EQUIVALENT I-131 but 5 4.0 wC1/ gram for l more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or > 4.0 yC1/ gram, be in at least HOT SHUTOG81 with the main steam line isolation valves closed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2. > 100/l wC1/ gram, be in at least NOT SHUTDOW with the main l steamiine isolation valves closed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00W within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. In CONDITION 1, 2, 3 or 4,

1. With the specific activity of the primary coolant > 0.2

- yCi/ gram DOSE EQUIVALENT I-131 or > 100/L yC1/ gram, perform the sampling and analysis requirements of Item 4b of Table 4.4.5-1 at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months until the specific activity of the primary coolant is restored to within its limits.

NATCM - WIT 2 3/4 4-10 Proposed TS/00604/8402-1 l

l l

RE ACTOR COOLANT SYSTEN LINITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

2. With:

a) THERMAL POWER changed by more than 155 of RATED THERMAL POWER in one hour, or b) The of f-gas level, at the SJAE, increased by more than 10,000 y C1/sec. in one hour at release rates less than 75,000 y C1/sec. or c) The off-gas level, at the SJAE, increased by more than 155 in one hour at release rates greater than 75,000 v C1/sec.,

perform the sampling and analysis requirement of Item 4C raf Table 4.4.5-1.

1

$URVEILLANCE REQUIREMENTS 4.4.5 The specific activity of the reacter coolant shall be demonstrated to be within the limits by perforasnce of the sampling and analysis program of Table 4.4.5-1.

NATCu - Uu!T 2 3/4 4-11 Proposed TS/0060g/s402-1

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3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 HIGH PRESSURE COOLANT INJECTION SYSTEM LIMITINGCON0iTIONFOROPERATION

, 3.5.1 The High Pressure Coolant Injection (HPCI) system shall be OPERABLE with:

a. One OPERA 8LE high pressure coolant injection pump, and 4

b. An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water to the reactor pressure vessel.

APPLICABILITY: COWITIONS 1*, 2* and 3* with reactor vessel steam dome pressure > 150 psig.

ACTION:

a. With the R/CI system inoperable, POWER OPERATION may continue

, and the provisions of 3.0.4 do not apply *, provided the RCIC system, ADS, CSS and LPCI system are OPERABLE; restore the inoperable HPCI system to OPERABLE status within 14 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 and reduce reactor steam dome pressure to s 150 psig within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. With the surveillance requirements of Specification 4.5.1 not performed at the required frequencies due to low reactor steam pressure, the provisions of Specification 4.0.4 are not applic-able provided the appropriate surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the tests. ,

SURVEILLANCE REQUIWENTS l

4.5.1 The HPCI shall be demonstrated OPERA 8LE:

a. At least once per 31 days by:

1 1. Verifying that the system piping from the pump discharge valve to the system isolation valve is filled with water, and

See Special Test Esception 3.10.5 i

HATCH - UNIT 2 3/4 5-1 Proposed TS/0058q/8402-1 l

i

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 LOW PRESSURE CORE COOLING SYSTEMS CORE SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.5.3.1 Two independent Core Spray System (CSS) subsystems shall be OPERABLE with each subsystem comprised of:

a. One OPERABLE CSS pump, and

b. An OPERABLE flow path capable of taking suction from at least one of the following OPERABLE sources and transferring the water through the spray sparger to the reactor vessel;

1. In CONDITION 1, 2 or 3, from the suppression pool.

2. In CONDITION 4 or 5*;

a) From the suppression pool, or b) When the suppression pool is being drained, from the condensate storage tank containing at least 150,000 gallons of water.

APPLICABILITY: CONDITIONS 1, 2, 3, 4, and 5*.

ACTION

a. In CONDITION 1, 2 or 3;

1. With one CSS subsystem inoperable, POWER OPERATION may continue provided both LPCI subsystems are OPERABLE; restore the inoperable CSS subsystem to OPERABLE status 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 and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. With both CSS subsystems inoperable, be in at least HOT SHUTOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the

! next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . .

The core spray systen and the suppression chamber are not required to be OPERABLE provided that the reactor vessel head is removed and the cavity is flooded, the spent fuel pool gates are removed, and the water level is maintained within the limits of Specification 3.9.9 and 3.9.10.

HATCH - UNIT 2 3/4 5-4 Proposed TS/0058q/8402-1

EMERGENCY CORE COOLING SYSTEMS LOW PRESSURE COOLANT INJECTION SYSTEM LIMITING CONOJTION FOR OPERATION 3.5.3.2 Two independent Low Pressure Coolant Injection (LPCI) sub-systems of the residual heat removal system (RHR) shall be OPERABLE with each subsystem comprised of:

a. Two OPERABLE RHR pumps,

b. An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water to the reactor pressure vessel.

APPLICABILITY: CONDITIONS 1, 2, 3, 4* and 5*, **.

ACTION:

a. In CONDITION 1, 2 or 3;

1. With one LPCI subsystem or one LPCI pump inoperable, POWER OPERATION may continue provided both CSS subsystems are OPERABLE; restore the inoperable LPCI subsystem or pump to OPERABLE status within 7 days or be in at least HOT SHUTDJWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT-DOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ,

2. With both LPCI subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and either be in COLD SHUTDOWN ,

or maintain reactor coolant temperature s 400*F by use '

of alternate heat removal methods within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3. With the LPCI system cross-tie valve open or power not removed from the valve operator, be in at least HOT SHUTDOWN with 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l l

l

b. In CONDITION 4* or 5*, ** with one or more LPCI subsystems l

inoperable, take the ACTION required by Specification 3.5.3.1.

The provisions of Specification 3.0.3 are not applicable.

l

Not applicable when two CSS subsystems are OPERABLE per Specification .

3.5.3.1.

- Not applicable when the LSS is not required to be OPERABLE per Specification 3.5.3.1.

HATCH - UNIT 2 3/4 5-7 Proposed TS/0058q/8402-1 l

i CONTAINMENT SYSTEMS ;

SURVElllANCE REQUIREMENTS (Continued)

b. If any periodic Type A test fails to meet either .75 La, or

.75 Lt. the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet either .75 L a or .75 L t a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet either .75 La or .75 Lt . at which time the above test schedule may be resumed.

c. The accuracy of each Type A test shall be verified by a supplemental test which:

1. Confirms the inccuracy of the test by verifying that the !

difference between the supplemental data .ind the Type A test data is within 0.25 La or 0.25 Lt .

2. Has a duration sufficient to establish accurately the change in leakage rate between the type A test and the supplemental tilst, and

3. Requires the quantity of gas injected into the contain-

, ment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of, the ;

total measured leakage at aP , 57.5 psig, or Pt . 28.8 psig.

d. Type 8 and C tests

thall be conducted at Pa, 57.5 osia, at l intervals no greater than 24 months except for tests involving:

1. Air locks, which shall be tested and demonstrated OPERA 8LE per Surveillance Requirement 4.6.1.3, and

2. Main steam line isolation valve:i, which shall be leak tested at least once per it months.

1

e. All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be per-formed to select a balanced integrated leakage measurement system.

f. The provisions of Specification 4.0.2 are not applicabit.

All Type 8 and Type C Leakage Tests (i.e., Local Leak Rate Tests) that fail

'l (i.e., test leakage is such that an LER would be required) during an outage shall be reported according to 10 CFR 50.13 by one 30-day written report that is due within 30 days of the first leakage test failure in the outage. All other leakage test failures discovered during the outage will be reported in a revision to the original report due within 30 days af ter the end of the !

outage.

i 4

HATCH - UNIT 2 3/4 6-5 Proposed TS/0059q/8402-1

p:

f.

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d CONTAINMENT SYSTEMS ,

PRIMARYCONTAiNMENTSTRdCTURALINTEGRITY LIMITING CON 0! TION FOR OPERATION d

/

3.6.1.5, The structural integrity of the primary containment shall be maintaine'd at a level consistent with the acceptance criteria in Speci-i fication 4.6.1.5.

APPLICABILITY: CONDITIONS 1, 2, and 3.

ACTION;.

, W$th the structural integrity of the primary' containment not conforming

, to the above requirements, restore the structural integrity to within

- , the limits prior to increasing the Reactor Coolent System temperature above 212'F.

SURVEILLANCE REQUIREMENTS 4.6.1.5 The structural integrity of the primary containment shall be determinen during the shutdown f.or each Type A containment leakage rate test by a visual inspection of the accessible interior and exterior i surfaces of'the containment and verifying no apparent changes in appear-ance of the surfaces or other abnormal degradation.

i t

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3 HATCH - UNIT 2 3/4 6-8 Proposed TS/0059q/8402-1

4 s

R t,

19 ELECTRICAL POWER SYSTEMS N' , SURVEILLANCE REQUIREMENTS (Continued) s . . > t 1 4.8.1.1.4 Reports - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to 10 CFR 50.73 or Specification s 6.9.2, as applicable. If the number of failures in the last 100 valid tests, on a per nuclear unit basis, is 2 7,. the report shall be supplemented to include the addftional information recommended in Regulatory Position C.3.b of Regulatory Guide,1.108, Revision 1, August 1977.

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/ HATCH - UNIT 2 3/4 8-7 Proposed TS/0062q/8402-1

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ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate.

QU,0 RUM 6.5.1.5 The minimum quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or designated Chairman and four voting members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Review Board shall be responsible for:

a. Review of (1) all procedures required by Specification 6.8 and i

changes thereto, (2) any other proposed procedures or changes thereto as determined by the General Manager-Plant Hatch to affect

nuclear safety,

b. Review of all proposed tests and experiments that affect nuclear safety.

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

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety,

e. Investigation of all violations of the Technical Specifications

, including the preparation and forwarding of reports covering I evaluation and recommendations to prevent recurrence to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations and to the Safety Review Board (SRB).

l f. Review of all REPORTABLE EVENTS. . l

g. Review of unit operations to detect potential nuclear safety hazards.

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the General Manager-Plant Hatch or the SRB.

1 1

i HATCH - UNIT 2 6-6 Proposed TS/0063q/8402-1

ADMINISTRATIVE CONTROLS QUORUM 6.5.2.6 The minimum quorum of the SRB necessary for the performance of the SRB review and audit functions of these Technical Specifications shall consist of the Chairman or Vice Chairman and at least 3 SRB members. No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW 6.5.2.7 The SRB shall review:

a. The safety evaluations for (1) changes to procedures, equipment or systems and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety questior, as defined in Section 50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes tu Technical Specifications or this Operating License.

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

g. All REPORTABLE EVENTS. I

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

j

1. Reports and meetings minutes of the Plant Review Board.

HATCH - UNIT 2 6-9 Proposed TS/0063q/8402-1

1 ADMINISTRATIVE CONTROLS

k. The Radiological Environmental Monitoring Program and the results thereof annually.

1. The 00CM, PCP, and implementing procedures biennially.

AUTHORITY f

6.5.2.9 The SR8 shall report to and advise the Executive Vice President -

Power Supply on those. areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.

4 RECORDS l .

6.5.2.10 Records of SRB activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each SRB meeting shall be prepared, approved and forwarded to the Executive Vice President-Power Supply within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Executive Vice

' President-Power Supply within 14 days following completion of the review,

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Power Supply and to the

management positions responsible for the areas audited within 30

days after completion of the audit.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and/or a report submitted pursuant i

to the requirements of Section 50.73 to 10 CFR 50.73, and I b. Each REPORTABLE EVENT shall be reviewed by the PR8, and the results I

of this review shall be submitted to the SRB and the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations. . .

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT SHUT 00WN within two hours.

b. The Safety Limit violation shall be reported to the Commission as soon as practical and in all cases within one hour of occurrence.

The Manager Nuclear Generation or the Vice President and General Manager Nuclear Operations and the SR8 shall be notified within 24 l hours.

! HATCH - UNIT 2 6-11 Proposed TS/0063c/8402-1 L .

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATI0N (Continued)

c. A Licensee Event Report shall be prepared pursuant to 10CFR50.73.

d. The Licensee Event Report shall be submitted to the Commission in

. accordance with 10CFR50.73, and to the PRB, the SRB, and the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations within 30 days of the violation. l 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix 'A' of Regulatory CJide 1.33, Revision 2, February 1978,

b. Refueling operations, j c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

i j g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Each procedure of 6.8.1 and other procedures which the General i.

Manager - Plant Hatch has determined to af fect nuclear safety, and changes thereto, shall be reviewed by the PRB and approved by the appropriate member i

of plant senagement, designated by the General Manager - Plant Hatch, prior l to implementation. The General Manager - Plant Hatch will approve administrative procedures, security plan implementing procedures, emergency plan implementing procedures and changes thereto. All other procedures of this specification and changes thereto will be approved by the department head designated by the General Manager - Plant Hatch. The procedures of this

specification shall be reviewed periodically as set forth in administrative

procedures. -

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

j 1

j HATCH - UNIT 2 6-12 Proposed TS/00760/8402-1

ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and En'orcement unless otherwise noted.

START-UP REPORT 6.9.1.1 A sumary report of plant start-up and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The start-up report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.

6.9.1.3 Start-up reports shall be submitted within (1) 90 days following completion of the start-up test program, or (2) 90 days following resumption or commencement of commercial power operation, or (3) 12 months following initial criticality, whichever is earliest. If the Start-up Report does not cover all three events (i.e., initial criticality, completion of start-up test program, and resumption or commencement of comercial operation),

supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS * .

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be subeltted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

A single submittal any be made for a multiple unit station. The submittal should combine those sections that are comon to all units at the station.

HATCH - UNIT 2 6-13 Proposed TS/0063q/8402-1

ADMINISTRATIVE CONiROLS ANNUAL REPORTS (Continued) 6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel, including contractors, receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,8 e.g., reactor operations and surveillance inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and

-refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 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 shall be assigned to specific major work functions,

b. Documentation of all challenges to safety / relief valves.

c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5. The following i information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine was reduced to less than the limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiofodine isotope concentration in microcuries per gram as a furction of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit,

d. Any other unit unique reports required on an annual basis. l ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORTea:

6.9.1.6 Routine radiological environmental surv'eillance reports covering '

the radiological environmental surveillance activities related to the plant during the previous calendar year shall be submitted prior to May*1 of each year. A single report may fulfill this requirement for both units.

6.9.1.7 The Annual Radiological Environmental Surveillance Report shall j include summaries, interpretations, and statistical evaluation of the

a. A single submittal may be made for a multiple-unit station. The submittal should combine those sections common to all units at the station.

l *This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

HATCH - UNIT 2 6-14 Proposed TS/0063q/8402-1 i

ADMINISTRATIVE CONTROLS results of the radiological environmental surveillance activities for the reporting period, including (as appropriate) a comparison with the preoperational studies, operational controls, previous environmental surveillance reports, and an assessment of any observed impacts of the plant operation on the environment. The reports shall also include the results of the land use surveys required by Specification 3.16.2 of Unit 1 Technical Specifications and the results of licensee participation in the interlaboratory comparison program required by Specification 3.16.3 of Unit 1 Technical Specifications.

The Annual Radiological Environmental Surveillance Report shall include summarized and tabulated results in the format of table 6.9.1.7-1 of all radiological environmental samples taken during the report period, with the exception of naturally occurring radionuclices which need not be reported.

In the event that some results are not available for inclusion with the report, the report shall be submitted, noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as practicable in a supplementary report.

The reports shall also include the following:

a. Summary descriptian of the radiological environmental monitoring program.

b. Map of all sampling locations as keyed to a table indicating distances and directions from main stack.

4

c. Results of the licensee participation in the Interlaboratory Comparison Program.

! SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTia 6.9.1.8 Routine radioactive effluent release reports covering the operation -

of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

Any changes to the 00CM shall be submitted with the next semi-annual report in which the change (s) was made effective. In addition, a report of any major changes to the radioactive waste treatment systems shall Be submitted l with the monthly operating report for the period in which the evaluation was reviewed and accepted by the Plant Review Board.

l

a. A single submittal may be made for a multiple-unit station. The submittal should combine those sections that are common to all units at the station; however, the submittal shall specify the releases of radioactive material from each unit.

I HATCH - UNIT 2 6-14a Proposed TS/0063q/8402-1 l

l ____--.____ _ _

i j

4 j

a i

i TABLE 6.9.1.7-1 i

f x ENVIRONMENTAL RADIOLOCiP.AL N0allTORIIRC PROGRAM SuletARY l >

y Mees of Facility rdwin i un t.ch bluc lea r P l an t Docket No. 50-328. 50-366 m

Location of Facility Aeoline Countw Georgia Reporting Period c

z Location of M Highest Annual Mean

" Medium or Type and j Pattway Sampled Total Number Lower Llelt All Indicator Name Control Nuot>e r o f 4 (Unit of of Analyses of Locations Distance, Mean Locations REPORTABLE Mea surement) Pe rfo rmed Detection 8** Mean Range and Direction Range **

8 Mean Range EVENTS l 1

l 4

l

}

e I

N b

1 I

e j

l I

1 i

j T 1 M o

i o i

=

1

ADMINISTRATIVE CONTROLS

e. Type of container, e.g. , LSA, type A, type B, large quantity

f. Solidification agent, e.g. , cement.

The Radioactive Effluent Release Report shall include (on a quarterly basis) unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents that were in excess of 1 C1, excluding dissolved and entrained gases and tritium for liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous releases.

The Radioactive Effluent Release Report shall include any changes to the PROCESS CONTROL PROGRAM and to the OFFSITE DOSE CALCULATION MANUAL made during the reporting period.

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the Regional Office of Inspection and i

Enforcement no later than the 15th of each month following the calendar month covered by the report.

i l

f HATCH - UNIT 2 6-14d Proposed TS/0063q/8402-1

S

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i i

1 i

HATCH - UNIT 2 6-15 Proposed TS/0063q/8402-1

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HATCH - UNIT 2 6-16 Proposed TS/0063q/8402-1

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Ofrector of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. Special reports for fire protection equipment operating and surveillance requirements shall be submitted, as required, by the Fire Hazards Analysis and its Appendix B reoutrements.

6.10 RECORD RETENTION in addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety,

c. ALL REPORTA8LE EVENTS submitted to the Consission. l

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications,

e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments,

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modif t-cations made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

HATCil - UNIT 2 6-17 Proposed TS/00634/8402-1

4.0 Special Surveillance and Study Activities 4.1 Erosion Control Inspection 4.2 Unusual or Important Events Requirements i

Reevirements

The licensee shall be alert to the occurrence of unusual or ;

important events. Unusual or important events are those that cause potentially significant environmental impact or could be

of public interest concerning environmental impact from plant l- operation. The following are examples: unusual or important i j bird impaction events on cooling tower structures or i meteorological towers, onsite plant or animal disease outbreaks, ,

unusual mortality of any species protected by the Endangered

] Species Act of 1973, fish kills near the HNP site, and j significant violations of relevant permits and certifications.

Actions Should an unusual or important event occur, the licensee shall

} make a prompt report to the NRC as required by 10 CFR 50.72 or 10 CFR 50.73.

l Bases Prompt reporting to the NRC of unusual or important events, as described, is necessary for responsible and orderly regulation ,

! of the nation's system of nuclear power reactors. The i- information thus provided may be useful or necessary to others concerned with the same environmental resources. Prompt :

knowledge and action may serve to alleviate the magnitude of environmental impact or to place it into a perspective broader than that available to the licensee. The NRC also has an i obligation to be responsive to inquiries from the public and the i 4

news media concerning potentially significant environmental events at nuclear power stations.

4.3 Enceedine Limits of Other Relevant Permits

^

Requirements , i

! The Itcensee shall notify the NRC of occurrences exceeding the i limits specified in relevant permits and certificates issued by i

! other Federal, State, and local agencies that are reportable to

! the agency that issued the permit. This requirement shaII apply

only to topics of NEPA concern within the NRC area of 4 responsibility as identified in the Environmental Technical Specifications (ETS).

I i ,

i j HATCH - UNIT 2 4-1 Proposed TS/0064q/8402-1 L . - -- - . - -

This requirement shall commence with the cate of issuance of the operating license *for Unit 2 and continue until approval for modification or termination is obtained from the NRC in accordance with section 5.6.3.

Action The licensee shall r.ake a report to the NRC in the event of a REPORTABLE EVENT exceeding a limit specified in a relevant l permit or certificate issued by another Federal, State, or local agency. The report shall be submitted within the time limit specified by the reporting requirements of the corresponding certification or permit issued pursuant to Section 401 or 402 of PL 92-500. The report will consist of a copy of the report made to the Georgia Department of Natural Resources, Environmental Protection Division.

Bases i The NRC is required under NEPA to maintain an awareness of environmental impacts causally related to the construction and operation of facilities licensed under its authority. Further, some of the ETS requirements are couched in terms of compliance with relevant permits, e.g., the NPDES permit, issued by other licensing authorities. The reports of exceeding limits of relevant permits also alert the NRC staff to environmental problems that may require mitigative action.

HATCH - UNIT 2 4-2 Proposed TS/0064c/8402-1

.a

5.6.2 Nonroutine Reports Deleted. Refer to 10 CFR 50.72 and 10 CFR 50.73 for reporting requirements.

/

[

1 5.6.3 Channes in Environmental Technical Specifications and Permits 5.6.3.1 Channes in Environmental Technical Spectfications Requests for changes in ETS shall be subettted to the NRC for review and authorization in accordance with 10 CFR 50.90. The request shall include an evaluation of the environmental impact of the proposed change and a supporting justification.

Implementation of such requested changes in ETS shall not commence prior to incorporation by the NRC of the new specifications in the Itcense.

HATCH-UNIT 2 5-8 Proposed TS/0065q/8402-1

v t e Letter Sequence Other
TAC:55713, (Open) TAC:55714, (Open)
Initiation Request Acceptance... Administration Questions Answers Results Approval... Other: ML20212H439
MONTHYEAR1987-02-13 [Table View]

ML20212H439

Text

SUMMARY

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