Text

Proposed Tech Specs,Modifying Existing Reporting Requirements,In Response to Generic Ltr 83-43, Reporting Requirements of 10CFR50,Sections 50.72 & 50.73 & Sts
	ML18092A133
Person / Time
Site:	Salem
Issue date:	03/27/1984
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18092A132	List: ML18092A131; ML18092A133;
References
	GL-83-43, NUDOCS 8404180128
	Download: ML18092A133 (49)
	v • d • e

CHANGES TO UNIT NO. 1 TECHNICAL SPECIFICATIONS

I

9.

INDEX DEFINITIONS SECTION 1.0 DEFINITIONS DEFINED TERMS *********************

ACTION *.*.** * **.******

AXIAL FLUX DIFFERENCE CHANNEL CALIBRATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CONTAINMENT INTEGRITY CONTROLLED LEAKAGE * * * * * * *

CORE ALTERATION ************* * ******

DOSE EQUIVALENT I-131 E-AVERAGE DISINTEGRATION ENERGY ENGINEEREn SAFETY FEATURE RESPONSE TIME FREQUENCY NOTATION * * * * * * *

GASEOUS RADWASTE TREATMENT SYSTEM. * * * * * * * * * * * *

IDENTIFIED LEAKAGE *********************

MEMBER{S) OF THE PUBLIC *******************

OFFSITE DOSE CALCULATION MANUAL {ODCM) * *

OPERABLE - OPERABILITY * * *

OPERATIONAL MODE * * * * * * *

PHYSICS TESTS PRESSURE BOUNDARY LEAKAGE. * * * * * *

PROCESS CONTROL PROGRAM {PCP). * * * *

PURGE-PURGING

. QUADRANT POWER TILT RATIO RATED THERMAL POWER ***************

REACTOR TRIP SYSTEM RESPONSE TIME

* ~

REPORTABLE EVENT * * *

SHUTDOWN MARGIN. * * * * ~ *

SITE BOUNDARY SOLIDIFICATION *

~ * * * * * * * * * * * *

SOURCE CHECK * * *

STAGGERED TEST BASIS * * * * * * * *

THERMAL POWER UNIDENTIFIED LEAKAGE

UNRESTRICTED AREA ******* * * * *

VENTILATION EXHAUST TREATMENT SYSTEM *

VENTING **************

SALEM - UNIT 1 I

PAGE 1-1 1-1 1-1 1-1 1-1 1-1 1-2 1-2 1-2 1-2 1-3 1..;3 1-3 1-3 1-3 1-4 1-4 1-4 1-4 1-5 1-5 1-5 1-5 1-5 1-5 1-6 1-6 l

1-6 1-*6 1-6 1-6 1-6 1-7 1-7 1-7 1-7 1-7

INDEX ADMINISTRATIVE CONTROLS SECTION 6.5.3 SAFETY REVIEW GROUP **...................

6.6 REPORTABLE EVENT ACTION..................

6.7 SAFETY LIMIT VIOLATION *

. 6.8 PROCEDURES AND PROGRAMS..................

6.9 REPORTING REQUIREMENTS

. 6.9.1 ROUTINE REPORTS ***

6.9.2 SPECIAL REPORTS 6.10 RECORD RETENTION.........

6.11 RADIATION PROTECTION PROGRAM................

6.12 HIGH RADIATION AREA **..................

6.13 PROCESS CONTROL PROGRAM..................

6.14 OFFSITE DOSE CALCULATION MANUAL..............

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.16 ENVIRONMENTAL QUALIFICATION.................

SALEM - UNIT 1 XIX PAGE 6-12 6-12 6-12 6-13 6-15 6-19 6-19 6-21 6-21 6-22 6-22 6-23 6-24

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its* trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENTS 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73' to 10CFR Part 50.

SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.

SOLIDIFICATION 1.30 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.

SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

-STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, SALEM - UNIT 1 1-6

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a.

~ 1.0 µCi/gram DOSE EQUIVALENT I-131, and

b.

~ 100/E µCi/gram.

APPLICABILITY:

MODES 1, 2, 3, 4 and 5 ACTION:

MODES 1, 2 and 3*

a.

With the specific activity of the primary coolant> 1.0 µCi/gram DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided that operation under.

these circumstances shall not exceed 10 percent of the unit's total yearly operating time.

The provisions of Specification 3.0.4 are not applicable.

b.

With the specific activity of the primary coolant> 1.0 µCi/gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one con-tinuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with Tavg < 500°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With the specific activity of the primary coolant > 100/E

µCi/gram, be in at least HOT STANDBY with Tavg < 500°F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 1, 2, 3, 4 and 5

a.

With the specific activity of the primary coolant> 1.0 µCi/gram DOSE EQUIVALENT I-131 or> 100/E µCi/gram, perfonn the* sampling and analysis requirements of item 4a of Table 4.4-2 until the specific activity of the primary coolant is restored to within its 1 imits. A REPORTABLE EVENT sha 11 be prepared and I

submitted to the Co1T1Tiission pursuant to Specification 6.9.1.

This report shall contain the results of the specific activity

analyses together with the following information:

With T

> 500°F.

avg -

SALEM - UNIT l 3/4 4-20

. e* ----------------------

-~----

3/4.12 - RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4~12.l MONITORING PROGRAM LIMITING CONDITION FOR OPERATION ACTION:

(Cont'd) than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations req~ired by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.8., identify the cause of the unavailability of samples and the f

_new location(s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report.

Include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

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

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations specified in the ODCM and shall be analyzed pursuant to the requirements of Table 4.12-1.

SALEM - UNIT 1 3/4 12-2

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2. A land use cen.sus shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animalA the nearest residence and the nearest garden* of greater than SO m2 (SOO ft.') produc~ng broad leaf vegetation.

(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of S km (3 miles) the locations in each of the 16 meteorological sectors of all milk animals and all gardens of greater than SO m2 producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of a Licensee Event Report, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.12.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via) the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1,.add the new location(s) to the radiological environmental monitoring program within 30 days.

The sampling location(s), excluding the control station location~ having the lowest calculated dose or dose commitment(s) (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was*

conducted.

In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.8, identify the new location(s) iri t8e next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) and t~ble for the ODCM reflecting the new location(s).

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

Broad le~f vegetation sampling of at least thre~ different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qa vegetation sampling lin Table 3.12-l.4c shall be followed, including analysis of control samples.

SALEM - UNIT 1 3/4 12-11

____ ---..,._. *--*-* ---*-** --------~--

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS (Cont'd)

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of.the land use ce~sus shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1. 7.

SALEM - UNIT 1 3/4 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3.

INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be perform~d on radioactive materials supplied as part of an Interlabora~ory Comparison Program wh)ch has been approved by the Commission.

APPLICABILITY:

At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to

.Specification 6.9.1.7 *

b.

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

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required*

Interlaboratory Comparison Program and in accordance with the ODCM shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1. 7.

SALEM - UNIT 1 3/4 12-13

ADMINISTRATIVE CONTROLS

d.

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

e.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear and to the Chairman of the Nuclear Review Board.

f.

Review of all REPORTABLE EVENTS.

g.

Review of facility operations to detect potential nuclear safety hazards.

h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear Review Board.

i.

Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Review Board.

j *.. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Review Board.

k.

Review of every unplanned onsite release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President ~

Nuclear and to the Nuclear Review Board.

1.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

AUTHORITY 6.5.1.7 The Station Operations Review Committee shall:

a.

Recommend to the General Manager - Salem Operations written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President -

Nuclear and the Nuclear Review Board of disagreement between the SORG and the General Manager - Salem Operations; however, the General Manager - Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

SALEM - UNIT 1 6-8

. J

ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.2.5 The NRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 The m1n1mum quorum of NRB necessary for the performance of the NRB review and audit functions of these technical specifications shall consist of the Chairman or his designated alternate and at least 4 NRB members including alternates~ No more than a minority of the quorum shall have line responsi-bility for operation of the facility.

REVIEW 6.5.2.7 The NRB 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 unrevi-ewed safety question.

b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section ~0.59~ 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.

e.

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

f.

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

g.

All REPORTABLE EVENTS.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

i.

Reports and meetings minutes of the Station Operations Review Committee.

AUDITS

6. 5. 2.8 Audits of facility activities shall be performed under the cognizance of the NRB.

These audits shall encompass:

SALEM - UN IT 1 6-10

ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.l The following actions ~hall bQ taken for REPORTABLE EVENTS:

a.

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

b.

Each REPORTABLE EVENT shall be reviewed by the SORG and the resultant Licensee Event Report submitted to the NRB and the Vice President -

Nuclear.

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 STANDBY within one hour.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour~ The Vice President - Nuclear and the NRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the SORG.

This report shall describe ( 1) applicable circumstances preceding the. violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective-action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commis-sion, the NRB and the Vice President - Nuclear within 14 days of the violation.

SALEM -

UN IT 1 6-12a

J ADMINISTRATIVE CONTROLS

~--------------------------------------------------------~-----------*

d.

Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System Subcooling Margin.

This program shall include the following:

. (i) Training of personnel, and (ii) Procedures for monitoring.

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 Administra-tor 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 different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

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

ANNUAL REPORTSl/

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~

l; 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.

SALEM - UNIT 1 6-15

ADMINISTRATIVE CONTROLS 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,2/* 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.

The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the Director, Office of Management Informa-tion _and Program Analysis, U.S. Nuclear Regulatory_ Commission, Washington, D.C.

20555, with a copy of the Regional Office of OI&E, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6.9.1.7 Routine Radiological Environmental Operating Reports covering the

.J operation of the unit during the previous calendar year shall *be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report ~eriod, including a comparison with preoperational studies with operational controls (as appropriate), and with previous environmental surveilance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by*

Specification 3.12.2.

Z/

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

SALEM - UNIT 1 6-16

ADMINISTRATIVE CONTROLS The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all meas-urements taken during the period pursuant to the Table and Figures in the envi-ronmental radiation section of the ODCM; as well as summarized and tabulated re-sults of locations specified in these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position~ Revision 1, November 1979.

In the event that some individual 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 possible in a supplementary report.

The reports shall also include the following:

a summary description of the radiological environmental monitoring program; at least two legible maps** cov-ering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.1; and dis-cussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.9.1.8 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous.six months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The Radioactive Effluent Release Reports shall include a summary. of the quanti-ties of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21.

"Measuring, Evaluating, and

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, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

- In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plant, 11 Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

SALEM - UNIT 1 6-17

ADMINISTRATIVE CONTROLS The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.*** This same report shall include an assessment of the radiation doses due to the radioactive. liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) ~uring the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.

The meteorological conditions concurrent with the time of release of r~dioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be.used for determining the gaseous pathway doses.

The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL.

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Radioactive Efflu~nt Release Reports shall include the following information for each class of solid waste (as defined by 10 CRF Part 61) $hipped offsite during the report period:

a.

Container volume,

b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal

d.

Source o,f waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

- - In lieu of submission with the first half year Radioactive Effluent Release Report, the lice~see has the opti6n of retaining this summa~ of required meteorological data on site in a file that shall be provided to the NRC upon request.

SALEM - UNIT 1 6-18

ADMINISTRATIVE CONTROLS

--~-----------------------------------------------------------------------------

e.

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f.

Solidification agent or absorbent (e.g., cement, ureaformaldahyde).

The Radioactive Effluent Release Reports shall include a list ~f description of unplanned releases from the site ta UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall incl~de any changes made during the reporting period to the PROCESS CONTROL PROGRAM {PCP) and to the OFFSITE DOSE CALCULATION MANUAL {ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Administrator. of the Regional Office within the time period specified for each report.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of*

Federal Regulations, the following records.shall be retined 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 REPORTABLE EVENTS.

d.

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

e.. Records of reactor tests and experiments.

f.

Records of changes made to Operating Procedures required by

Specification 6.8.1.

g.

Records of radioactive shipments.

h.

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

i.

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

SALEM - UNIT 1 6-19

ADMINISTRATIVE CONTROLS 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 modifications made to systems and equipment.described in the Final Safety Analysis Report.

b.

Records of new and irradiated fue 1 inventory, fue 1 transfers* and assembly burnup histories.

c., Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those facility components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

Records of training arid qualification for current members of the pl ant staff.

h.

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

i.

Records of Quality Assurance activities required by the QA Manual.

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 SORC and the NRB.

1.

Records for Environmental Qualification which are covered under the provisions of Paragraph 6.16.

m.

Records of the service 1 i ves of all hydraulic and mechanical snubbers listed on Tables 3.7-4a and 3.7-4b including the date at which the service life commences and associated installation and maintenance records.

n.

Records. of secondary water sampling and water quality.

o.

Records of analyses required by the radiological environmental monitoring program which 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 followed.

SALEM - UNIT 1 6-20

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM 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.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the "control device" or 11alann signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20; each high radiation area in which the intensity of radiation 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 controlled by issuance of a Radiation Exposure Permit*.

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 facility 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 doo~s to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Senior Shift Supervisor on duty and/or Senior Supervisor - Radiation Protection. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit 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

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 areas.

SALEM - UNIT 1 6-21

ADMINISTRATIVE CONTROLS

~--------------

a dose in excess of 1000 mrem** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonable constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a war.ning device.

In lieu of the staytime specification of the RWP, direct or remote (such as use ~f closed circuit TV cameras) continuous surveillance 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) 6.13.1 The PCP shall be approved by the Commission prfor to implementation.

6.13.2 Licensee initiated changes.to the PCP:

1.

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of addi ti anal *or supplemental information;

b.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and*

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORG.

2.

Sha 11 become_ effective upon review and acceptance by the SORG.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The OOCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM:

1.

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change' without benefit of additional or supplemental information.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided *with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

- Measurement made at 18 11 from source of radioactivity.

SALEM - UNIT 1 6-22 1

ADMINISTRATIVE CONTROLS *

~--------~-----------------

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and

c. Documentation of the fact that the change has been reviewed and found acceptable by th~ SORC.

2.

Shall become effective upon* review and acceptanc*e by the SORC.

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT

svsTEMS 6.15.1 Licensee initiated *major changes to the radioactive waste system (liquid, gaseous and solid):

1.

Shall be reported to the Commission in the FSAR for the period in which the evaluation was reviewed by (SORC).

The discussion of each changes shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59;

b. Sufficient detailed information to totally support the reason for the ~hange without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

d.

An evalu~tioh of the change, which shows.the predicted releases of radioactive m~terials in liquid and gaseous effluents a~d/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;*

e.

An evaluation of the change, which shows the expected maximum exposures to-individual in _the unrestricted area and to the general population that differ from those previously estimated in the license application and amendm~nts thereto;

f.

A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

g.

An estimate of the exposure to plant operating personnel as a result of the change; and

h.

Documentation of the fact that the change was reviewed and found acceptable by the (SORC).

2.

Sha 11 become effective upon review and acceptance by the SORC.

SALEM - UNIT 1 6-23

ADMINISTRATIVE CONTROLS 6.16 ENVIRONMENTAL QUALIFICATION 6.16.1 By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:

Division of Operating Reactors "Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors" (DOR Guidelines}; or, NUREG-0588 "Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment, 11 December 1979.

Copies of these documents are attached to Drder for Modification of License No. DPR-70 dated October 24, 1980.

6.16.2 By no later than December 1, 1980, complete and auditible records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588.

Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified SALEM - UNIT 1.

6-24

CHANGES TO UNIT NO. 2 TECHNICAL SPECIFICATIONS

INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS DEFINED TERMS 1-1 ACTION * * * * * * * * * * * * * * * * * * * * * * *

1-1 AXIAL FLUX DIFFERENCE 1-1 CHANNEL CALIBRATION

~ * * * * * * * * * * * * * * * * * *

1-1 CHANNEL CHECK 1-1 CHANNEL FUNCTIONAL TEST 1-1 CONTAINMENT INTEGRITY 1-2 CONTROLLED LEAKAGE * ~ * * * * * * * * * * * * * * * * * *

1-2 CORE ALTERATION 1-2 DOSE EQUIVALENT I-131 * * * * * * * * * * * * * * * * * *

1-2 E-AVERAGE DISINTEGRATION ENERGY 1-3 ENGINEERED SAFETY FEATURE RESPONSE TIME 1-3 FREQUENCY NOTATION * * * * * * * * *

1-3 GASEOUS RADWASTE TREATMENT SYSTEM. * * *

1-3 IDENTIFIED LEAKAGE ******* * * * * * * * * * * * * *

1-3 MEMBER{S) OF THE PUBLIC. * * * * * *

1-4 OFFSITE DOSE CALCULATION MANUAL {ODCM)

1-4 OPERABLE - OPERABILITY * * * * * * * * * * * * * * * * * *

1-4 OPERATIONAL MODE * * * * * * * * * * * * * * * * * * * * *

1-4 PHYSICS TESTS 1-5 PRESSURE BOUNDARY LEAKAGE. * * * * * * * * * * * * * * * *

1-5

PROCESS CONTROL PROGRAM {PCP). * * * * * * * * * * * * * *

1-5 PURGE-PURGING 1-5 QUADRANT POWER TILT RATIO 1-5 RATED THERMAL POWER 1-5 REACTOR TRIP SYSTEM RESPONSE TIME.

1-6 REPORTABLE EVENT * * * * * * * * * *

1-6 SHUTDOWN MARGIN. * * * * *

1-6 SITE BOUNDARY 1-6 SOLIDIFICATION * * * * * * * * * * * * * * * * * * * * * *

1-6 SOURCE CHECK * * * * * * * * * * * * * * *

1-6 STAGGERED TEST BASIS

1-6 THERMAL POWER 1-7 UNIDENTIFIED LEAKAGE * * * * * * * * * * *

1-7 UNRESTRICTED AREA 1-7

VENTILATION EXHAUST TREATMENT SYSTEM * * * * * * * * * * *

1-7 VENTING

***** ~

1-7 SALEM - UNIT 2 I

INDEX ADMINISTRATIVE CONTROLS SECTION 6.5.3 SAFETY REVIEW GROUP **...................

6.6 REPORTABLE EVENT ACTION..................

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

6.8 PROCEDURES AND PROGRAMS..................

6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS *....

6.9.2 SPECIAL REPORTS *...

6.10 RECORD RETENTION 6.11 RADIATION PROTECTION PROGRAM................

6.12 HIGH RADIATION AREA **..................

6.13 PROCESS CONTROL PROGRAM..................

6.14 OFFSITE DOSE CALCULATION MANUAL..............

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS SALEM -. UNIT 2 XIX PAGE 6-12 6-12a 6-12a 6-13 6-15 6-19 6-19 6-21 6-21 6-22 6-23

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its~trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENTS 1.27 A REPORTABLE EVENT shall be any of those conditions specified in_

Section 50.73 to 10CFR Part 50.

SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.

SOLIDIFICATION 1.30 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meet_s shipping and burial ground requirements.

SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment-of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, SALEM - UNIT 2 1-6 I

REACTOR COOLANT SYSTEM

. ACTION:

(Continued)

MODES 1, 2, 3, 4 and 5:

a.

With the specific activity of the primary coolant greater than 1.0 µCi/gram DOSE EQUIVALENT I-131 or greater than 100/£ µCi/gram, perform the sampling and analysis requirements of item 4a of Table 4.4-2 until the specific activity of the primary coolant is restored to within its limits. A REPORTABLE EVENT shall be f

prepared and submitted to the Commission pursuant to Specification 6.9. 1.

This report shall contain the results of the specific activity analyses together wi~h the following information:

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.

Fuel burnup by core region,

3.

Clean-up 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.

History of de-gassing operations, if any, 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, and

5.

The time duration when the specific activity of the primary coolant exceeded 1.0 µCi/gram DOSE EQUIVALENT I-131.

SURVEILLANCE REQUIREMENTS 4.4.9 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

SALEM - UNIT 2 3/4 4-24

~ --**---*---,

J 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION ACTION:

{Cont'd) than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

In lieu of a Licensee Event Report and pursuant ta Specification 6.9.1.8, identify the cause of the unavailability of samples and the new location(s) for obtaining replacement samples in the next -

Semiannual Radioactive Effluent Release Report.

Include in the report

.a revised figure(s) and table for the ODCM reflecting the new l acati on (s).

d.

The provisions of Specifications 3.0.3 and 3w0.4 are nat'applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations specified in the ODCM and shall be analyzed pursuant to the requirements of Table 4.12-1.

SALEM.;, UNIT 2 3/4 12-2

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the.location in each of the 16 meteorological sectors of the nearest milk animal~ the nearest residence and the nearest garden* of greater than 50 m2 (500 ft~) producing broad leaf vegetation.

(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the. land use census shall also identify within a distance of 5 km (3 miles) the locations*

in each of the 16 meteorological sectors of all milk animals and all gardens of greater than 50 m2 producing broad ieaf vegetation.

.. APPLICABILITY:. At all times.

ACTION:

a. With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated 'in Specification. 4.11.2.3, in lieu of* a Licensee Event Report-, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report. pursuant to Specification 6.9.1.12.

b.

With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via) the same exposure pathway) 20 percent greater than at a location from which samples are currently b~ing obtained.in accordance with ~pecificati-0n 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days.

The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commi.tment(s) (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year.in which this land use.~ensus ~as conducted.

In lieu of a Licensee Event Report and pursuant to Specification 6.9 *. 1. 8, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c.

The provisions of Specifications 3.Q.3 and 3.0.4 are not applicable.

Broad leaf vegetation sampling of.at leas't three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qa vegetation sampling lin Tab*le 3.12-1.4c shall be followed, including analysis*of control samples.

SALEM - UNIT 2 3/4 12-11

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS (Cont'd)

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such. as by a door-to-door survey, aerial survey, or* by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiol~gical Environmental Operating Report pursuant to Specification 6.9.1. i.

SALEM - UNIT 2 3/4 12-12

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3.

INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials suppl~ed as part of an Interlaboratory Comparison Program which has been approved by_ the Commission.

APPLICABILITY:

At all times.

ACTION:

a.

With analyses not being performed as required above, report the corrective actions taken to ~revent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.L 7.

I

b.

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

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM shall be included in the Annual.Radidlogical Envtronmental Operating Report pursuant to Specification 6.9.1. 7

l SALEM - UNIT 2

. 3/4 12-13

ADMINISTRATIVE CONTROLS

d.

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

e.

Investigation of all violations of the Technical Specifications including the preparatio~ and forwarding of reports c~vering

- evaluation and recommendations to prevent recurrence to the Vice President - Nuclear and to the Chairman of the Nuclear Review Board.

f.

Review of all REPORTABLE EVENTS.

g.

Review of facility operations to detect potential nuclear safety hazards.

h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Cha_i rman of the Nuclear Review Board.

i.

Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Review Board. *

j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Review Board.

k.

Review of every unplanned onsite release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent*

recurrence and the forwarding of these reports to the Vice President -

Nuclear and to the Nuclear Review Board.

1.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

AUTHORITY 6.5.1.7 The Station Operations Review Committee shall:

a.

Recommend to th~ General Manager - Salem Operati-0ns written approva) or disapproval of items considered under 6.5.1.6(a) through (d) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President -

Nuclear and the Nuclear Review Board of disagreement between the SORC and the General Manager - Salem Operations; however, the General Manager - Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

SALEM - UNIT 2 6-8

ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.2.5 The NRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months th.ereafter.

QUORUM 6.5.2.6 The m1n1mum quorum of NRB necessary for the performance of the NRB review and audit functions of these technical specifications shall consist -of the Chairman or his designated alternate and at least 4 NRB members including alternates.

No more than a minority of the quorum shall have line responsi-bility for operation of the facility.

REVIEW 6.5.2.7 The NRB 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 1 iCense.

e.

Violations of codes, regulations, orders, Technical Specifications, license requirement~, or of internal procedures or instruction having nuclear safety significance.

f~

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

g.

All REPORTABLE EVENTS.

h.

All recognized indications of an unanticipated deficiency in some

. aspect of design or operation of safety related structures, systems, or components.

i.

Reports and meetings minutes of the Station Operations Review Committee.

AUDITS

6. 5.2.8 Audits of facility activities shall be performed under the cognizance of the NRB.

These audits shall encompass:

SALEM - UNIT 2 6-10 f

ADMINISTRATIVE CONTROLS

~---------------------------------~------------------------.

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

a.

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

b.

Each REPORTABLE EVENT shall be reviewed by the SORC and the resultant Licensee Event Report submitted to th~ NRB and the Vice President -

Nuclear.

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 STANDBY withiri one hour.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within. one hour.

The Vice President - Nuclear and the NRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

A Safety limit Violation Report shall be prepared.

The report shall be reviewed by the SORC.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commis-sion, the NRB and the Vice President - Nuclear within 14 days of the violation.

SALEM - UNIT 2 6-12a

ADMINISTRATIVE CONTROLS

~----------------------------------------------------------------------

d.

Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Rea_ctor Coolant System Subcooling Margin.

This program shall include the following:

(i) Training of personnel, and (ii) Procedures for monitoring.

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 Administra-tor 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 different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the pl ant.

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 power operation), supplementary reports shall be submitted at least every three months until al 1 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 submitted prior to March 1 of each year.

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

I; 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.

SALEM - UNIT 2 6-15

ADMINISTRATIVE CONTROLS 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 thei~ associated man rem exposure according to work and job functions,2/ 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.

The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.6.5.b).

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the Director, Office of Management Informa-tion and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy of the Regional Office of OI&E, no later than *the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6.9.1.7 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to.May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperati onal studies with operational controls (as appropriate), and with previous environmental surveilance reports, and an assessment of the observed impacts of the pl ant operation on the en vi ron.ment.

The reports shall also include the results of land use censuses required by Specification 3.12.2.

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

SALEM - UNIT 2 6-16 l

ADMINISTRATIVE CONTROLS The Annual Radiological Environmentar Operating Reports shall include the results of analysis of all radiological environmental samples and of all meas-urements taken during the period pursuant to the Table and Figures in the envi-ronmental radiation_ section of the ODCM; as well as summarized and tabulated re-sults of locations specified in these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some individual 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 possible in a supplementary report.

The reports shall also include the following:

a summary description of the radiological environmental monitoring program; at least two legible maps** cov-ering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.1; and dis-cussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.9.1.8 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous six months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The Radioactive Effluent Release Reports shall include a _summary of the quanti-ties of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21.

"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plant, 11 Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

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, for uni ts with separate radwaste systems, the submittal sh al 1 specify the releases of radioactive material from each unit.

- In lieu of submission with the Annual Radiological En\\tronmental Operating Report, the licensee has the option of retaining this ~ummary of required meteorological data on site in a file that shall be provided to the NRC upon request.

SALEM - UNIT 2 6-17 r.

ADMINISTRATIVE CONTROLS The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected ove~ the previous year. This annual summary may be either in the form of an hour-by-hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.*** This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include. an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY {Figure 5.1-3) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.

The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL.

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely

most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

I The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CRF Part 61) shipped offsite during the report period:

a.

Container volume,

b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determine by measurement or estimate),

d.

Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

- - In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

SALEM - UNIT 2 6-18

ADMINISTRATIVE CONTROLS

e.

Type of container (e.g., LSA, Type A, Type B, Large Quantity}, and

f.

Solidification agent or a-bsorbent (e.g., cement, urea formal dahyde}.

The Radioactive Effluent Release Reports shall include a list of description of unplanned releases from the site to UNRESTRICTED AREAS of.radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Re1ease Reports shall include any changes made during the reportfog period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM}, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.9 The (Fxy } for RATED THERMAL POWER (Fxf'1} for all core planes containing bank "D" control rods and all unroddea core pl~nes and the plot of predicted (Fo T.PRel} vs. Axial* Core Height with the limit envelope shall be provided to the NRC Regional Administrator with a copy to Director of Nuclear Reactor Regulation, Attention: Chief, Core Performance Branch, U.S. Nuclear

Regulatory*Connnission, Washington, D.C. 20555 at least 60 days prior to each cycle initial criticality unless otherwise approved by the Commission by letter.

In addition, in the event that the limit should change requiring a new submittal or an amended submittal to the Peaking Factor Limit Report, it will be submitted 60 days prior to the date the limit would become effective unless otherwise approved by the Commission by letter.

Any information needed to support FxfPwill be by request from the NRC and need not be included in this report.

SALEM - UNIT 2 6-18a

ADMINISTRATIVE CONTROLS

~--------------------------------------

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Administrator of the Regional Office within the time period specified for each report.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retined 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 REPORTABLE EVENTS submitted to the Commission.

d.

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

e.

Records of reactor tests and experiments.

f.

Records of changes made to Operating Procedures required by Specification 6.8.1.

g.

Records of radioactive shipments.

h.

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

i.

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

SALEM - UNIT 1 6-19

ADMINISTRATIVE CONTROLS

~-------------------------------------------------------------------------

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 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 burnup histories.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those facility components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

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

h.

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

i.

Records of Quality Assurance activities required by the QA Manual.

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 SORC and the NRB.

l.

Records for Environmental Qualification which are covered under the provisions of Paragraphs 2.C(7) and 2.C(8) of Facility Operating License DPR-75.

m.

Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7-4a and 3.7-4b including the date at which the service life commences and associated installation and maintenance records.

n.

Records of secondary water sampling and water quality.

o.

Records of analyses required by the radial ogical environmental monitoring program which 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 followed.

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ADMINISTRATIVE CONTROLS

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6.11 RADIATION PROTECTION PROGRAM 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 inv'olving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the 11control device 11 or 11alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation 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 controlled by issuance of a Radiation Exposure Permit*.

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 in~egrated 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 facility 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 administrative control of the Senior Shift Supervisor on duty and/or Senior Supervisor - Radiation Protection. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit 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 accessibl~ to personnel with radiation levels such that a major portion of the body could receive in one hour

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 areas.

SALEM - UNIT 2 6-21

ADMINISTRATIVE CONTROLS a dose in excess of 1000 mrem** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no e~closure can be reasonable constructed around the individual areas; then that area shall be roped off, conspicuously posted and a fl ashing li.ght shall be activated as a warning device.

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

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

1.

Shall be submitted to the Commission in the Semiannual Radioactive

Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;

b.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2.

Shall become effective upon review and acceptance by the SORC.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM:

1.

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

a.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and.

provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

- Measurement made at 18 11 from source of radioactivity.

SALEM - UNIT 2 6-22

ADMINISTRATIVE CONTROLS

b.

A-determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and

c. Documentation of the fact that the change has been reviewed and approved in accordance with Specification 6.5.4.

2.

Shall become effective upon review and approval.

6.15 - MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS ANO SOLID WASTE TREATMENT SYSTEMS 6.15.* 1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid):

1.

Shall be reported to the Commission in the FSAR for the period in which the evaluation was reviewed by (SORC).

The discussion of each changes shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

d.

An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

e.

An evaluation of the change, which shows the expected maximum exposures to individual in the unrestricted area and to the general populatiori that differ from those previously estimated in the license application and amendments thereto;

f.

A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

g.

An estimate of the exposure to plant operating personnel as a result of the change; and

h.

Documentation of the fact that the change was reviewed and found acceptable by the (SORC).

2.

Shall become effective upon review and acceptance by the SORC.

SALEM - UNIT -2 6-23

-I

ENCLOSURE II Corrections to LCR 79 -

01, Rev. 1

TABLE 3.3-12 (Continued)

TABLE NOTATION

ACTION 26 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and

b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 27 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram:

a.

At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/

gram DOSE EQUIVALENT I-131.

ACTION 28 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram.

SALEM - UNIT 1 3/4 3-60

RADIOACTIVE EFFLUENTS BASES releases of radioactive material in gaseous effluents will be kept 11as low as is reasonably achievable." The ODCM calculational methods specified in Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the-guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, 11 Revision 1,

October 1977 and Regulatory Guide 1.111, 11Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from -

Light-Water Cooled Reactors, 11 Revision 1, July 1977.

These equations also provide for determining the actual dose based upon the historical average atmospheric conditions.

The release rate specifications for iodine-131, tritium, and radionuclides in particulate form with half-life greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of these calculations were:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

3/4.11.2.4 GASEOUS RAO~ASTE TREATMENT SYSTEM The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.O of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

SALEM - UNIT 1 B 3/4 11-5

~*

TABLE 3.3-12 (Continued)

TABLE NOTATION '

ACTION 26 -

With the number of channel~ OPERABLE less than required ~ the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and

b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 27 -

With the number of channels OPERABLE less than required ~ the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram:

. a.

At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/

gram DOSE EQUIVALENT I-131.

ACTION 28 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram.

SALEM - UNIT 2 3/4 3-55

r RADIOACTIVE EFFLUENTS BASES releases of radioactive material in gaseous effluents will be kept 11as low as is reasonably achievable.

11 Thg ODCM calculational methods specified in Surveillance Requi.rements implement the requirements in Section III.A of Appendix I that conformance with the* gui de*s of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, 11Calculation

,of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, 11 Revision 1, October 1977 and Regulatory Guide 1.111, 11Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, 11 Revision 1, July 1977.

These equations also provide for determining the actual dose based upon the historical average atmospheric conditions.

The release ~ate specifications for iodine-131, tritium, and radionuclides in particulate form with half-life greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of these calculations were:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable.

11 This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.O of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were*

specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

SALEM - UNIT 2 B 3/4 11-5

ML18092A133

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