ML20046D196

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Proposed Tech Specs Supporting Compliance W/New Requirements of 10CFR20 & 10CFR50.36a
ML20046D196
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/11/1993
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20046D192 List:
References
GNRO-93-00074, GNRO-93-74, NUDOCS 9308160288
Download: ML20046D196 (30)
v • d • e


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i to GhTO-93/00074 Page 1 of 16

- MARKED-UP TECIINICAL SPECIFICATIONS PAGES FOR TILE REVISED 10 CFR PART 20 and 10 CFR PART 50.36a (GGNS PCOL 93/06)

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. to GNRO-93/00074 I

Page 2 of 16 DEFINITIONS IDENTIFIED LEAKAGE 1.18 IDENTIFIED LEAKAGE shall be:

a.

Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or b.

Leakage into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the opera-tion of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

ISOLATION SYSTEM RESPONSE TIME 1.19 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required positions.

Times shall include diesel generator starting and sequence loading delays where applicable.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

LIMITING CONTROL ROD PATTERN 1.20 A LIMITING CONTROL R0D PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.

LINEAR HEAT GENERATION RATE 1.21 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod.

It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL TEST 1.22 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc., of a logic circuit, from sensor through and including the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

MAXIMUM FRACTION OF LIMITING POWER DENSITY 1.23 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core.

b e_rk \\ N (\\.M-G yay MEMBER (S) 0F THE PUBLIC

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1.24 MEMBER (S) 0F THE PUBLIC shall i clude al' persen: "he are not n

occupatiere'ly acccciated "ith the plant.

This category does net 4acade

-employees of the uti'ity, itc centracters er vendert.

^1sc excluded fre= this c-ategory are percent who enter the site te service equipment er te make del 4"-

cric;.

This category doc: include person; who use portions of thc sitt for recreatienal, cccupational or other purpece: net-a;;cciated with the plant.

GRAND GULF-UNIT 1 1-4

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, to GhWO-93/00074 Page 3 of 16 1

J Insert 1.24 be an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.

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. to GNRO.93/00074 Page 4 of 16 DEFINITIONS SHUTDOWN MARGIN 1.39 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is subtritical or would be subtritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e.

68 F; and xenon free.

epy j,,nch SITE BDUNDARY g,

7, 1.40 The SITE BOUN shall be that line beyond which the an is

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owned, leased otherwise controlled by the licensee.

1.41 DELETED 1.42 DELETED STAGGERED TEST BASIS 1.43 A STAGGERED TEST BASIS shall consist of:

A test schedule for n systems, subsystems, trains or other designated a.

components obtained by dividing the specified test interval into n equal subintervals.

b.

The testing of one system, subsystem, train or other designated com-ponent at the beginning of each subinterval.

THERMAL POWER 1.44 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

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UNIDENTIFIED LEAKAGE 1.45 UNIDENTIFIED LEAKAGE sh 1 all leakage which is not IDENTIFIED LEAKAGE.

UNRESTRICTED AREA uMr- \\M\\-d wor 1.46 An UNRESTRICTE EA shall be any area at er beyond the SITE BOUNDARY ac-cess to which is controlled by the licensee.fer purpose: Of protection Of-

-MEMSMS OF THE PUBLIC frem exposure-to-radiation and radioactive materiale, er-i duc-

= any :res vithin the41TE-BOUNDARY used4ee--residentia4-quarter cr for n

.-trial, commercial, institutional, 2nd/or4ecreation:1 purpc;cc.

W 1.47 DELETED GRAND GULF-UNIT 1 1-8 Amendment No. 87

. 13 GNRO-93/00074 Page 5 d M ADMINISTRATIVE CONTROLS n.,..A u.s. 3.B.z Ghagh PROCEDURESANDPROGRAMS(Continued) 2.

Limitations en the concentrations of radicactive material rele::cd in liquid effluent to UNRESTRICTED AREAS-conforming-

=tc 10 CFR Part 20, Appendix B, Table II, Columa 2, 3.

Monitoring sampling and analysis of radica f liquid and gaseouseffluentsin,accordancewith10CFR 0.

nd with the methodology and parameters in the ODCM, 1302.

4.

Limitations on the annual and quarterly doses or dose commitment to a MEMBER of the PUBLIC from radioactive materials in liquid effluents released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5.

Determinationofcumulativeandarojecteddosecontributions from radioactive effluents for tie current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6.

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the uidelines for the annual dose or dose commitment conform-ing to ppendix I to 10 7.

Limitation on the dose-rate result 4eg-from-radioaetive materim nd-the SITE SOUNDAPJ

-released in gaseous-effhents--to-areegh 1. CFR Part 20, Appen-to the dose: associated wit conformin$leII,ColumnI, a

dix B, Ta 8.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the SITE B0UNDARY conforming to-Appendix I to 10 CFR Part 50, 9.

Limitations on the annual and. quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritiura, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents releassd from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and 10.

Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

Radiological Environmental Monitoring Program e.

A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) repre-sentative measurements of radioactivity in the highest potential GRAND GULF-UNIT 1 6-15a Amendment No. 87

5 to GhTO-93/00074 I

Page 6 of 16 l

Insert 6.8.3.d.2 2.. Limitations on the concentrations of radioactive material released in liquid effluents for UNRESTRICTED AREAS conforming to ten times the concentration values in 10CFR Part 20.1001 - 20.2401, Appendix B, Table 2, Column 2.

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Insert 6.8.3.d.7

7. Limitations on the dose rate resulting from radioactive material released in gaseous efiluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:
a. For noble gases: Less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin, and, i
b. For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal 1500 mrem / year to any organ, t

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' to GNRO-93/00074 Page 7 cf 16

' ADMINISTRATIVE CONTROLS-STARTUP REPORTS (Continued)

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6. 9.1. 2 The startup 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 compari-son of these values with design predictions and specifications.

Any correc-tive 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 included 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 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 commercial operation, supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTSM

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

The initial report shall be submitted prior to March 1 of the year fol-lowing initial criticality.

6.9.1.5.1 Reports shall include a tabulation on an annual basis of the number l

' of station, utility, and other personnel, including' contractors, receiving exposures greater than 100 mrer/yr and their associated manrem exposure ac-cording to work and job functions,E e.g., reactor operations and surveil-lance, inservice inspection, routine maintenance, special maintenance (describe _ maintenance), watte processing, and refueling.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.

In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

6.9.1.5.2 Reports shall include documentation of all challenges to safety and relief valves.

6.9.1.5.3 Reports shall include the results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.5.

The fol-lowing information shall be included:

(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 the limit was exceeded, and results of one

. analysis after the radiciodine activity was reduced to less than the limit M single submittal may be made for a multiple unit station.

The submittal A

should combine those sections that are common to t at the station.

This tabulation supplements the requirements of Y20.407 cf 10 CIR I' art 20.

W tFR ~2.0/2 ~2 O(o -

GRAND GULF-UNIT 1 6-16 AmendmentNo.28l

. ta GNRO-93/00074 Page 8 of 16

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ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requircments of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

l 6.12 HIGH RADIATION AREA

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6. 2 1 In lie of t

" ontrol device" or " alarm signal" require ara each high radiation area in which the inten M graph-W

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CFR 20 ater t,han 100 mrem /hr but less than 1000 mrem /hr shall be barri-caded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).*

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

a.

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

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been,made knowledgeable of them.

c.

A health physics qualified individual, i.e., qualified in radiation protection procedures, with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the unit Health Physicist in the Radiation Work Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the admiris-

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trative control of the Shift Superintendent on duty and/or the unit Radiation Control Supervisor.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in i

  • Health Physics personnel or personnel escorted by Health Physics personnel i

shall be exempt from the RWP issuance requirement during the performance of l

their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

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GRAND GULF-UNIT 1 6-21 1

, to GNRO-93/00074 ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA (Continued) excess of 1000 mrem

  • that are located within large areas, such as the contain-ment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the RWP, continuous surveillance, direct or remote, such as use of closed circuit TV cameras, may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.'2n.

This documentation shall contain:

1)

Sufficient information to support the change together with the

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appropriate analyses or evaluations justifying the change (s) and 2)

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

5 hall become effective after review and acceptance by the PSRC and the approval of the General Manager, Plant Operations.

6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n.

This documentation shall contain:

1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and p g, 2)

A determination that the change will maintain th leve of radioactive effluent control required by 10 CFR 0.

CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CF r-O and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the PSRC and the approval of the General Manager, Plant Operations.

c.

Shall be submitted to the Commission in the form of a complete, le i o

of the entire ODCM as a part of or concurrent with the

~ annua adioactive Effluent Release Report for the period of the repoFt 'n which any change to the ODCM was made.

Each change shall entified by markings in the margin of the affected pages, e

clearly indicating the area of the page that was changed, and shall indicate the ate (e.g., month / year) the change was implementet 30 c.m

  • Measurement made at-18" from source of radioactivity.

GRAND GULF-UNIT 1 6-22 Amendment No. 87 i

Attachnient 3 to GNRO-93/00074

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3/4.11 RADI0 ACTIVE EFFLUENTS age 10 or 16 BASES 3/4.11.1 LIQUID EFFLUENTS I

3/4.11.1.4 LIQUID HOLOUP TANKS The tanks listed in this specification include all those tanks containing radioactive material that are not surrounded by liners, dikes, or walls capable of holding the contents and that do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table JET Column 2, at the nearest potable water supply and the nearest surface wate supply in an UNRESTRICTED AREA.

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i GRAND GULF-UNIT 1 B 3/4 11-1 Amendment No. 87

  • b GNRO-93/00074 Page 11 of 16

' ADMINISTRATIVE CONTROLS 6.10 RECORDRETENTION(Continued) 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:

Records and drawing changes reflecting unit design modifications made a.

to systems and equipment described in the Final Safety Analysis-Report.

b.

Records of new and irradiated fuel invento

, fuel transfers and assembly burnup histories,

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arnr14 niradiatinn ex osure for all i..dividuah enteeing radiation-c.

control areat.

d.

Records of gaseous iquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.

f.

Records of rea: tor tests and experiments.

g.

Records of training and qualification for current members of the unit staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the Operational Quality Assurance Manual not listed in Section 6.10.1.

j.

Records of rsviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PSRC and the SRC.

1.

Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

Records,of analyses required by the radiological environmental m.

monitoring program.

Records of reviews performed for changes made to the OFFSITE DOSE n.

CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

GRAND GULF-UNIT 1 6-20 Amendment No. 21, 87 j

. 13 GNRO-93/00074 INDEX Page 12 of 16 ADMINISTRATIVE CONTROLS SECTION EASE i

SAFETY REVIEW COMMITTEE (SRC)

(Continued)

Review.............................

6-10 Audits.............................

6-11 Authority............................

6-12 Records.............................

6-12

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6.5.3 TECHNICAL REVIEW AND CONTROL Activities...........................

6-12 6.6 REPORTABLE EVENT ACTION......................

6-13 6.7 SAFETY LIMIT VIOLATION......................

6-13 6.8 PROCEDURES AND PROGRAMS.....................

6-14 6.9 REPORTING REOUIREMENTS Routine Reports.........................

6-15 Startup Reports.........................

6-15 Annual Reports.........................

6-16 Annual Radiological Environmental Operating Report 6-17

'gnnual Radioactive Effluent Release Report 6-17 n

y perating Reports....................

6-19 Core Operating Limits Report (COLR)...............

6-19 S p ec i al. Rep o rts.........................

6-19a 6.10 RECORD RETENTION 6-19b 6.11 RADIATION PROTECTION PROGRAM..................

6-21 6.12 HIGH RADIATION AREA.......................

6-21 6.13 PROCESS PROGRAM CONTROL (PCP)..................

6-22 6.14 0FFSITE DOSE CALCULATION KANUAL (ODCM) 6-22

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1 GRAND GULF-UNIT 1 xx Amendment No. 87,106

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, to GNRO-93/00074 Page 13 of 16 DEFINITIONS MINIMUM CRITICAL POWER RATIO 1.25 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.

0FFSITE DOSE CALCULATION MANUAL (ODCM) 1.26 The OFFSITE DDSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program.

The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.3 and (2) descriptions of the informatioj)_that-s ld be included in the Annual Radiological Environmental' Operating andf&essannual Radioactive Effluent Release Reports required by SpecificationsJ6.9.t 6,

. 9.1. 7, 1

6.9.1.8 and 6.9.1.9.

OPERABLE - OPERABILITY 1.27 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and l

when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL CONDITION - CONDITION 1.28 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1.2.

PHYSICS TESTS 1.29 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear oaracte-is'.4.5 of the reactor core and related instrumentation and

1) described in Chapter 14 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE I

1.30 PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isolable-fault' in a reactor coolant system component body, pipe wall or vessel wall.

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GRAND GULF-UNIT 1 1-5 Amendment No. 87

i 3/4.11 RADI0 ACTIVE EFFLUENTS to GNRO-93/00074 3/4.11.1 LIOUID EFFLUENTS Page 14 of 16 LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside tempo-rary tank, not includirg liners for shipping radwaste, shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY:

At all times.

ACTION:

With the quantity of radioactive material in any of the above a.

specified tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tanks and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit and dec ribe the events leading to the condition in the nex emiannual Radioactive E

Effluent Release Report.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above specified tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

GRAND GU'LF-UNIT 1 3/4 11-1 Amendment No. 6, 87

- to GNRO 93/00074 DMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

6.9.1.7 The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectivesoutlinedin(1)theODCMand(2)SectionsIV.B.2,IV.B.3,andIV.C of Appendix I to 10 CFR Part 50.

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-SEMANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT e

.tioNf-t$Miannual-Radioactive-Eff4uent-Rele::: Report covering the opeg:-

6 9 1 8 ^ ^ *^- dur4ng-the-previous 4-months-of-operat3on chall be-subm.tt-

-*iein-60-days-after January 1 and-,luly 1 cf each year.

6.9.1.9 The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The mate-i r

rialprovidedshallbe(1)consistentwiththeobjectivesoutlinedintheODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appen-dix I to 10 CFR Part 50.

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GRAND GULF-UNIT 1 6-17 Amendment No. 87 l

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, to GNRO-93/00074 i

Page.16 of 16 j

Insert 6.9.1.8 l

The Annual Radioactive EfIluent Release Report covering the operation of the unit I

during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

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  • to GNR0-93/00074 Page 1 of 14

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PROPOSED TECHNICAL SPECIFICATION PAGES FOR THE REVISED 10 CFR PART 20 AND 10 CFR PART 50.36a (Information Only)

(GGNS PCOL-93/06) 1

  • to GNRO-93/00074 Page 2 of 14 DEFINITIONS IDENTIFIED LEAKAGE 1.18 IDENTIFIED LEAKAGE shall be:

a.

Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or b.

Leakage into the drywell atmosphere from sources that are both

{

specifically located and known either not to interfere with the opera-i tion of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

l ISOLATION SYSTEM RESPONSE TIME 4

1 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when-the l.19 monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel-generator starting and sequence loading delays where applicable. The i

l response time may be measured by any series of sequential, overlapping or total l

steps such that the entire response time is measured.

1 LIMITING CONTROL ROD PATTERN 1.20 A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the core-being on a thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.

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LINEAR HEAT GENERATION RATE 1.21 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod.

It is the integral of the heat flux over the heat transfer area -

1 associated with the unit length.

l LOGIC SYSTEM FUNCTIONAL TEST i

1.22 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e.,

all relays and contacts, all trip units, solid state logic elements, etc., of a logic circuit, from sensor through and including the actuated device, to verify i

OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

MAXIMUM FRACTION OF LIMITING POWER DENSITY 1.23 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core.

J MEMBER (S) 0F THE PUBLIC i

i 1.24 MEMBER (S) 0F THE PUBLIC shall be an ivividual in a controlled or unrestricted

)

area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.

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.I GRAND. GULF-UNIT 1 1-4 Amendment No.

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  • ' to GNRO-93/00074 Page 3 of 14 e

DEFINITIONS SHUTDOWN MARGIN 1.39 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is subtritical or would be subcritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be j

fully withdrawn and the reactor is in the shutdown condition; cold, i.e. 68'F; and xenon free.

SITE B0UNDARY 1.40 The SITE B0UNDARY shall be that line beyond which the land or property is not.

1 owned, leased, or otherwise controlled by the licensee.

j 1.41 DELETED l

1.42 DELETED i

STAGGERED TEST-BASIS 1.43 A STAGGERED TEST BASIS shall consist of:

i a.

A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals.

I b.

The testing of one system, subsystem, train or other designated com-l ponent at the beginning of each subinterval.

l THERMAL POWER 1.44 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

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UNIDENTIFIED LEAKAGE 1.45 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.

l UNRESTRICTED AREA l.46 An UNRESTRICTED AREA shall be any area access to which is neither limited nor i

controlled by the licensee.

1,47 DELETED l

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I GRAND GULF-UNIT 1 1-8 Amendment No. 87,-

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  • to GNRO-93/00074 Page 4 of 14 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 2.

Limitations on the concentrations of radioactive material released in liquid effluents for UNRESTRICTED AREAS conforming to ten times the concentration values in 10CFR Part 20.1001 -

10.2401, Appendix B, Table 2, Column 2.

3.

Monitoring, sampling, and analysis of radioactive. liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM, 4.

Limitations on the annual and quarterly doses or dose commitment to a MEMBER of the PUBLIC from radioactive materials in liquid effluents released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5.

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6.

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these-systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR Part 50, 7.

Limitations on the dose rate resulting from radioactive.

material released in gaseous offluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:

a.

For noble gases:

Less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin, and, b.

For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:

Less than or equal 1500 mrem / year to any organ, 8.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the SITE B0UNDARY conforming to Appendix I to 10 CFR Part 50, 9.

Limitations on the annual and quarterly do.ses to a MEMBER OF THE 'PUBLIC from Iodine-131, Iodine-133, tritium, and all GRAND GULF-UNIT 1 6-15a Amendment No. 87, e

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  • to GNR0-93/00074 Page 5 of 14 i

1 ADMINISTRATIVE CONTROLS i

PROCEDURES AND PROGRAMS'(Continued) radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit to areas beyond the SITE B0UNDARY conforming to Appendix I to 10 CFR Part 50, and 10.

Limitations on the. annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to

.{

radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

e.

Radiolooical Environmental Monitorina Proaram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall l

provide (1) representative measurements of radioactivity in the highest potential

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GRAND GULF-UNIT 1 6-15b Amendment No. 87,

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  • to GNR0-93/00074-Page 6 of 14 ADMINISTRATIVE CONTROLS STARTUP rep 0RTS (Continued) 6.9.1.2 The startup 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 specifications. 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 included 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 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 commercial operation, supplementary reports shall be submitted at least every three months until all three events have been completed.

l ANNUAL REPORTS '

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

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5.1 Reports shall include 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 manrem exposure according to work and job functions,2r e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.

In the aggregate, at least.80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

6.9.1.5.2 Reports shall include documentation of all challenges to' safety and relief valves.

6.9.1.5.3 Reports shall include the results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.5.

The fol-lowing information shall be included:

(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 the limit was exceeded, and results of one analysis after the radiciodine activity was reduced to less than the limit "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.

2/This tabulation supplements the requirements of 10 CFR 20 2206.

1 GRAND GULF-UNIT 1

.6-16 Amendment No. 28, i$

  • .to GNR0-93/00074 Page 7 of 14 ADMINISTRATIVE CONTROLS l

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

l s

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the "cnntrol device" or " alarm signal" required by 10CFR20.1601(a) each high radiation area in which the intensity of radiation j

is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be l

controlled by requiring issuance of a Radiation Work Permit (RWP).* Any i

individual or group of individuals permitted to enter such areas shall be i

provided with or accompanied by one or more of the following:

a.

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

b.

A radiation monitoring device which continuously integrates the i

radiation dose rate in the area and alarms when a preset t

integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the 1

area has been established and personnel have been made

-knowledgeable of them.

l c.

A health physics qualified individual, i.e., qualified in radiation protection proceduras, with a: radiation dose rate monitoring device, who'is responsible for providing positive control over the activities witnin the area and shall perform periodic radiation surveillance at the frequency specified by the unit Health Physicist in the Radiation Work Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to

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personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with ll locked doors to prevent unauthorized entry, and the keys shall be. maintained i

under the administrative control of the Shift Superintendent on duty and/or i

the unit Radiation Control Supervisor. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum -

allowable ' stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in

  • Health Physics personnel or personnel. escorted by Health Physics personnel shall be exempt from the RWP-issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation -

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areas.

GRAND GULF-UNIT _1 6-21 Amendment No.

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  • to GNR0-93/00074 Page 8 of 14 ADMINISTRATIVE CONTROLS E

6.12 HIGH RADIATION AREA (Continued)

Excess of 1000 mrem

  • that are located within large areas, such as the containment, where no enclosure exists for purposes of locking, and no enclosure can be i

reasonably constructed around the individual areas, then that area shall be roped t

off, conspicuously posted and a flashing light shall be activated as a warning j

device.

In lieu of the stay time specification of the RWP, continuous surveillance, j

direct or remote, such as use of closed circuit TV cameras, may be made by personnel qualified in radiation protection procedures to provide positive. exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained

]

as required by Specification 6.10.2n.

This documentation shall contain:

l 1)

Sufficient information to support the change together with the-l appropriate analyses or evaluations justifying the change (s) and j

2)

A determination that the change will maintain the overall l

conformance of the solidified waste product to existing i

requirements of Federal, State, or other applicable regulations, i

P b.

Shall become effective after review and acceptance by the PSRC and the l

approval of the General Manager, Plar,t Operations.

6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)

Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n.

This documentation shall contain:

2 1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR l

Part 190, 10 CFR 50.36a, Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.

b.

Shall become effective after review and acceptance by the PSRC and the approval of the General Manager, Plant Operations.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual l

Radioactive Effluent Release Report for the period of '.he report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month / year) the change was implemented.

  • Measurement made at 30 cm from source of radioactivity.

GRAND GULF-UNIT 1 6-22 Amendment No. 87,

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  • to GNR0-93/00074 Page 9 of 14

-j 3/4.11 RADI0 ACTIVE EFFLUENTS f

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BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.4 LIOUID HOLDUP TANKS l

The tanks listed in this specification include all those tanks containing radioactive material that are not surrounded by liners, dikes, or walls capable of holding the contents and that do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the

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event of an uncontrolled release of the tanks' contents, the resulting i

concentrations would be less than the limits of 10 CFR Part 20, Appendix B, _ Table 2, l

Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

GRAND GULF-UNIT 1 B 3/4 11-1 Amendment No. 87,

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-c a

.m to GNR0-93/00074 Page 10 of 14.

i ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION (Continued) d.

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

1 i

e.

Records of changes made to the procedures required by Specification j

6.8.1.

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f.

Records of radioactive shipments.

l g.

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

[

-t h.

Records o annual physical inventory of all. sealed source material

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c of record.

6.10.2 The following records shall be retained for the duration of the Unit j

Operating License:

t a.

Records and drawing changes reflecting unit design modifications made to l

systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and j

assembly burnup histories.

a c.

Records of radiation exposure as required by 10CFR20.

i d.

Records of gaseous and liquid radioactive material released to the:

environs.

e.

Records of transient or operational cycles for those unit components 1

identified in Table 5.7.1-1.

l r

f.

Records of reactor tests and experiments.

g.

Records of training-and qualification for current members of the f

unit staff.

.i h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the Operational Quality Assurance Manual not listed in Section 6.10.1.

j.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PSRC and the SRC.

i 1.

Records of the service lives of all hydraulic and mechanical snubbers-including the date at which the service life commences and associated installation and maintenance records.

t m.

Records of analyses required by the radiological environmental i

monitoring program.

n.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

t GRAND GULF-UNIT 1 6 Amendment No. 21, 87,

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  • to GNR0-93/00074

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Page 11 of 14.

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l JNDEX j

i ADMINISTRATIVE CONTROLS i

a i

SECTION PAGE' SAFETY REVIEW COMMITTEE (SRC)

(Continued) l r

Review.......................................................

6-10 Audits...................................................

6 Authority....................................................

6-12 Records......................................................

6-12 6.5.3 TECHNICAL REVIEW AND CONTROL i

Activities...................................................

6-12 6.6 REPORTABLE EVENT ACTI0N.........................................,...

6-13 i

6.7 SAFETY LIMIT VIOLATION..............................................

6-13 I

6.8 PROCEDURES AND PR0 GRAMS.............................................

6-14z t

-l 6.9 REPORTING REQUIREMENTS

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Routine Reports..............................................

6-15 Startup Reports..............................................

6 i i

Ann u al Re p o r t s............................................... 6-16 Annual Radiological Environmental Operating Report........... 6-17 P

l. f Annual Radioactive Effluent Release Report...................

6-17.

Monthly Operating Reports....................................

6-19 l

Core Operating Limits Report (C0LR)..........................

6-19

-j S p e c i al Re p o rt s.............................................. 6 - 19 a

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t 6.10 RECORD RETENTION..................................................

6-19b

-i 6.11 RADIATION PROTECTION PR0 GRAM.......................................

6-21 6.12 HIGH' RADIATION AREA..............

................................. 6-21 6.13 PROCESS PROGRAM CONTROL (PCP)'......................................

6-22 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM).............................

'6-22 GRAND GULF-UNIT 1 xx Amendment No. 106, i

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. Attachment 4 to GNRO-93/00074 Page 12 of 14 DEFINITIONS'

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i MINIMUM CRITICAL POWER RATIO 1.25 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists.

l in the core.

r 0FFSITE DOSE CALCULATION MANUAL (ODCM) 1.26lThe OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and-i

. parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.3 and (2) descriptions of the information that should be included.in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release l

Reports required by Specifications 6.9.1.6, 6.9.1.7, 6.9.1.8 and 6.9.1.9.

OPERABLE - OPERABILITY 1.27 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

t OPERATIONAL CONDITION - CONDITION I

1.28 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as j

specified in Table 1.2.

l P_HYSICS TESTS f

1.29 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and i

1) described in Chapter 14 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

i PRESSURE BOUNDARY LEAKAGE 1.30 PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isolable fault in a reactor coolant system component body, pipe wall or vessel wall.

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GRAND GULF-UNIT 1 1-5 Amendment No. 87,

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'I to GNR0-93/00074

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Page 13 of 14 3/4.11 RADI0 ACTIVE EFFLUENTS i

3/4.11.1 LIOU1D EFFLUENTS l

l LIOUID HOLDUP TANKS i

LIMITING CONDITION FOR OPERATION l

3.11.1.4 The quantity of radioactive material contained in any outside temporary tank, not including liners for shipping radwaste, shall be limited Eto i

less than or equal to 10 curies, excluding tritium and dissolved or entrained j

noble gases.

APPLICABILITY: At all times.

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ACTION:

a.

With the quantity of radioactive material in any of the above' specified tanks exceeding the above limit, immediately suspend all j

additions of radioactive material to the tanks and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to the condition in the next Annual Radioactive l

Effluent Release Report.

l b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS i

4.11.1.4 The quantity of radioactive material contained in each of the above l

specified tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days' when j

radioactive materials are being added to the tank.

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I GRAND GULF-UNIT 1 3/4 11-1 Amendment No. 87,

.i A

operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

6.9.1.7 The report shall include summaries, interpretations, and analysis of -

trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l

6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

I 6.9.1.9 The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

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GRAND GULF-UNIT 1 6-17 Amendment No. 87,

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