ML20067C043

Proposed Tech Specs Incorporating New Requirements of 10CFR20

ML20067C043
Person / Time
Site:	Comanche Peak
Issue date:	02/14/1994
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20067C039	List: ML20067C043
References
NUDOCS 9402250276
Download: ML20067C043 (14)

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ATTACHMENT 3 TO TXX-94045 AFFECTED TECHNICAL SPECIFICATION PAGES (NUREG-1468) REVISED BY ALL APPROVED-LICENSE AMENDMENTS Note:

Numbers in page margin correspond to the proposed changes as identified in Section 11 of

!. " Description of Technical Specification Change Request *. These numbers are provided only as an aid to the reviewer in matching the description and analysis discussion with the affected pages.

The.

numbers are ng1 part of the proposed changes.

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- 9402250276 940214

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DEFINITIONS Me. //7 fed I EMBMf,SWF THE$BL T.18dEMBER(S)0FTFEPUBLICshallincludeallpesonswho t-ectuTnt-Opb tional nyssocLated with the plant.

Thi tego s not incl de employees of the licensee, N tracto vendors. Als excluded from this category

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are persons who en Aht s te-to-sp vice equipment or to make eliveries.

j who use ort 4ws the site for recre-oses not associ (ated with-t This catego es include persons 3tjen1 C occupational, or other pur ant.

OFFSITE DOSE CALCULATION MANUAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (ODCM) 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 l

Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4.

OPERABLE - OPERABILITY 1.20 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).

OPERATIONAL MODE - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generato~ tube leakage) through a nonisolable f ault in a Reactor Coolant System component j

body, pipe wall, or vessel wall.

COMANCHE PEAK - UNITS 1 AND 2 1-4

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i I-to TXX-94045 i

Page 2 of 13 I

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.1.18 MEMBER (S) 0F THE PUBLIC means an individual in a controlled or l M 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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Nhc/wnf 3 h 7W-ffGY6 Ope 3 0F0 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLVENTS 3/4.11.1 LIOUID HOLDUP TANKS The tanks listed in this specification include all those unprotected outdoor tanks both permanent and temporary that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Restricting the quantity of radioactive material contained in the speci-fied tanks provides assurance that in the event of an uncontrolled release of the tank's contents J' A ETTClFTin f0], the refulting concentntionsaould be less than the wDeF'siippTF arid'ihe n{earisGurf ace water supply in an UNRESTRIC l

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3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits of hydrogen and oxygen.

Automatic control features are included in the system to prevent the hydrown and oxygen concentrations from reaching these flammability limits.

These automatic control features include isolation of the source of hydrogen and/or oxygen.

Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of 10 CFR Part 50 Appendix A.

r 3/4 11.2.2 GAS STORAGE TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE B0UNDARY will not exceed 0.5 rem. This is consistent with Standard Review Plan 11,3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System J

Leak or Failure," in NUREG-0800, July 1981.

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5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The Exclusion Area shall be as shown in Figure 5.1-1.

LOW POPULATION ZONE 5.1.2 The Low Population Zone shall be as shown in Figure 5.1-2.

MAP DEFINING UNRESTRICTED AREAS AND SITE BOU LIOUID EFFLUENTS 5.1.3 will allow identification of structures and release poin tion of UNRESTRICTED AREAS within the SITE BOUNDAR MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-3.

The definition of UNRESTRICTED AREA used in implement n O$3 Specifications has been expanded over that in 10 CFR i&3'a'Q.9he ne echnical UNRESTRICTED AREA boundary may coincide with the Exclus on Are l

\\\\L defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not inc

, as over water bodies.

The concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utilized in the Limiting Conditions for to keep levels of radioactive materials in liquid and gaseous effluents as lo as is reasonably achievable, pursuant to 10 CFR 50.36a.

5.2 CONTAINMENT CONFIGURATION 5.2.1 of cylindrical shape, with a dome roof and having th features:

Nominal inside diameter - 135 feet.

a.

b.

Nominal inside height - 192.5 feet.

260 feet)

(Dome = 67.5 feet; total -

Nominal thickness of concrete walls - 4.5 feet, c.

d.

Nominal thickness of concrete roof - 2.5 feet, Nominal thickness of base mat - 12.0 feet.

e.

f.

Nominal thickness of steel liner wall - 3/8 inch.

Base Mat = 1/4 inch), and (Dome - 1/2 inch, g.

Het free volume - 2,985,000 cubic feet.

COMANCHE PEAK - UNITS I AND 2 5-1

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ADMINISTRATIVE CONTROLS I

i PROCEDURES A M PROGRAMS (Continued) b.

In-Plant Radiation Monitorina (Continued _)

2)

Procedures for monitoring, and 3)

Provisions for maintenance of sampling and analysis equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation and low pressure turbine disc stress corrosion cracking.

This program shall include:

1)

Identification of a sampling schedule for the critical variables and control points for these variables, 2)

Identification of the procedures used to measure the values of the critical variables, 3)

Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, 4)

Procedures for the recording and management of data, 5)

Procedures defining corrective actions for all off-control point chemistry conditions, and 6)

A procedure identifying:

(a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d.

Post-Accident Samolina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the following:

1)

Training of personnel, 2)

Procedures for sampling and analysis, an,d i

3)

Provisions for maintenance of sampling and analysis equipment.

Radioactive Effluent Controls Procram e.

A program shall be provided confonsing with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBl.IC from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall COMANCHE PEAK - UNITS 1 AND 2 6-15

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ADMINISTRATIVE CONTROLS

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PROCEDURES AND PROGRAMS (Continued) e.

Radioactive Effluent Controls Procram (Continued) be implemented by operating procedures, and (3) shall include remedial-actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the i

ODCM, l

2)

Limitations on the concentrations of radioactive material i

// O fimes 7/e rele 3 f.asedhujd_ effluents _to_UN8ESIRICTED AREAS con Q9 Wn Marjd L I

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Monitoring, sampling, and analysis of radioactge_ liquid and

%d/c 2 C#/v"W2 gaseous effluents in accordance with 10 CFR!gnd with the j

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methodology and parameters in the ODCM, Q

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Limitations on the annual and quarterly doses or70se commitment

%f to a MEMBER OF THE PUBLIC from radioactive eaterials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR 50, 5)

Determination of cumulative and projected dose contributions from radioactive affluents 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 por-tions of these systems are used to reduce releases of radioactiv-ity 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 I to 1 CDL50 h the site.

8o 7)

Limitations on the dose rate resul om radioactive aterial

/Q released in gaseous effluents to areas {beyond the SITE BOUNDARY

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O conforming togdeseFITs521TtNFWTth~mFC k

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8)

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

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131. Iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR 50, and COMANCHE PEAK - UNITS 1 AND 2 6-16

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TS 6.8.3e.7) (continued) a.

For noble gases:

Less than or equal to a dose rate of 500 mrem /yr to 9 \\g,-

the total. body and less than or equal to a dose rate of 3000 mrem /yr 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 i

equal to a dose rate of 1500 mrem /yr to any organ.

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fl p. 1 # l.3 ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued)

The initial Startup Report shall address each of the startup tests identified in Chapter 14 of the Final Safety Analysis Report 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 specificaticns.

Any corrective actions that were required to obtain satis-factory operatio's shall also be described.

Any additional specific details required in license conditions based on other comitments shall be included in this report.

Subsequent Startup Reports shall address startup tests that are necessary to demonstrate the acceptability of changes and/or modifications.

Startup Reports shall be submitted within:

(1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or comencement of comercial 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 comencement of comercial operation), supplementary reports shall be sub-mitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS

• 6.9.1.2 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 fear.

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

Reports required on an an,nua sha c du basis ofih~e%Ter o

• ^*f"'I ON a.

A tabulation on an nnua station, utilit,Ic"F j,

greater th @an 100 m@re( neluding contractors)freceiving @ip6sTrW and otherf Wi jobfuncti@ons**e.g.,reacoroperationsanlisuMg a's43iiPE and the associated

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according to work an 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, thermoluminescent dosimeter (TLD), or film badge measurements.

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

In the aggre-gate, at least 80% of the totalg@iflifiiia~for work functions;e-be%y-d s

sources should be assigned to pec c) y collecGe.

eaf ;

Jose. epvakn+

y (reported w pers+ rern )

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

• • This tabulation supplements the requirements of 10 CFR q'V COMANCHE PEAK - UNITS 1 AND 2 6-18 pggg

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ID 06 ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.g.2 In additien to the applicable reporting requirements of Title 10. Code of Federal Regulations, special reports shall be submitted to the Regional Admin-istrator of the Regional Office of the NRC within the time period specified for each report.

6.10 RECORD RETENTION 6.10.1 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.

6.10.2 The following records shall be retained for at least 5 years:

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

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; d.

Records of surveillance activities, inspections, and calibrations required by the Technical Specifications, Technical Requirements Manual, and Fire Protection Report, except as explicitly covered in jg Specification 6.10.3; I*

e.

Records of changes made to the procedures required by gg

, Specification 6.8.1; f.

-Records-of-radictetive shipments, g.

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

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

6.10.3 The following records shall be retained for the duration of the unit Operating Licenses a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report; b.

Records of new and irradiated fuel inventory, fuel transfers, and assembly bu up-t Jos es(s,tglat;Q re w a Sr wh o m Reeords of rTlilitYeE53fe'iire-fe all individuals endrir,g iediatier, G hd3 c.

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unons & st uns re1mm ;

o d.

Records of gaseoO afilfTiqu s^r13toire ve material released to the environs; COMNCHE PEAK - UNITS 1 AND 2 6-22 Unit 1 - Amendment No. 1 l

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/2 ADMINISTRATIVE CONTROLS-RECORD RETENTION (Continuedi t

Records of transient or operational cycles for those unit components-e.

identified in Table 5.7-1; l

f.

Records of reactor tests and experiments; g.

Records of training and qualification for current members of the unit i

staff; h.

Records of inservice inspections performed pursuant to these Technical Specifications; i.

Records of quality assurance activities required by the Quality Assurance Manual; s

J.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 1

10 CFR 50.59; k.

Records of meetings of the 50RC and the ORC; 1.

Records of the service lives of all hydraulic and mechanical snubb'ers required by the Technical Requirements Manual including the date at which the service life commences and associated installation and maintenance records; Records of sgcondary water sampling and water quality; m.

Records of analyses required by the Radiological Environmental Moni-n.

toring Program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effective at specified times and QA records showing that these procedures were i

followed; and Records of reviews performed for changes made to the OFFSITE DOSE o.

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

6.12 HIGH RADIATION AREA g

3 6.12.1 Pursuant to paragraph 10 CFR " :"0';' );, in lieu of the "contro device" or "alars signal" required by paragrap 10 CFR 40.00; W,-each high radiation area, as defined in 10 CFR_20 M ich the intensity of radiation i

is equal to or less than 1000<"* " " - 'l* iWfrom the radiation source l

i or from any surface which the rad a ion pene rates shall be barricaded and conspicuously posted as a high radiation area and entr c t et sh _Q,1ut ~ --

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COMANCHE PEAK - UNITS 1 AND 2 6-23 i

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• ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA (Continued) controlled by requiring issuance of a Radiation Work Permit (RWP).

Indi-viduals qualified in radiation protection procedures (e.g., Radiation Protec-tion Technician) or personnel continuously escorted by such individuals ma be exempt from the RWP issuance requirement duri rmance of thei dese.

assigned du ies in high radiation areas with a es equal to or le than 100Q provided they are otherwise fo ing plant radiation protection m

procedur6s or entry into such high radiation areas. 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; or 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 levels in the area have been estab-lished and en made knowledgeable of them; or l

M, e 3 c.

An individual qualif e' n ra lation protection procedures with a radiation dose rate monitoring device, who is responsible for pro-viding positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the RWP.. da, AdaN5 ni 6.12.2 In addi M n to the requirements of Specification 6.12.1 reas acces-sible to MC with radiation levels greater than 1000

@ _ Y fNfu Y radiation source or from any surface which the ra on penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or radiation protection su ervision.

Doors shall remain which shall specify the dose rate levels rYfie under an approved RWP l

locked except during periods of access b s na-n moediate work areas and the maximum allowable stay time for individua in that area.

In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be ade byO-~--- qualified in radiation I l protection procedures to provide positive exposur M 1 over the activities be m1med within the area.

74 g3 Fo high radiation areas accessible to :rcane with radiation leve s o greater than 1000 that are located w hn arge areas, such as I

PWR containment, where no qm@elosure exists for purposes of locking and where no p closure can be reasonably constructed around the LMS area,, that QqC area shall be arricaded, conspicuously posted, rand a flashing light sha 1 be activated as a warning device.

sd ded mrem lh af 30 cm b k les s ren@ d 30 cm

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, Aape. gnf LS S E NISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

Shall be documented and records of reviews performed shall be retained a.

as required by Specification 6.10.30.

This documentation shall contain:

1)

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

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.

Shall become effective after review and acceptance by the SORC and the approval of the Vice President,, Nuclear Operations.

6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the 00CM:

Shall be documented and records of reviews performed shall be retaLined a.

as required by Specification 6.10.30.

This documentation shall contain:

1)

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

A determination that the change will maintain the level of TD i

radioactive effluent control required by 10 CFR 204 i

190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and no 40 CFR impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the SORC and the approval of the Vice President, Nuclear Operations.

1 Shall be submitted to the Commission in the form of a complete.

c.

legible copy of the entire ODCM as a part of or concurrent with the Seelannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each chan identffled by markings in the margin of the affected pages,ge shall be clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

i COMANCHE PEAK - UNITS 1 AND 2 6-25

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