Text

Amend 22 to License NPF-86,revising App a TS Re Reporting Radioactive Effluent Releases from Facility
	ML20056G136
Person / Time
Site:	Seabrook
Issue date:	08/16/1993
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; North Atlantic Energy Service Corp
Shared Package
ML20056G137	List: ML20056G136; ML20056G138;
References
	NPF-86-A-022 NUDOCS 9309020118
	Download: ML20056G136 (20)
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UNITCD STATES

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-l NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D C. 20555-0001 NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL*

DOCKET NO. 50-443 SEABROOK STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-86 1.

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

A.

The application for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated January 13, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

North Atlantic Energy rvice Corporation (NAESCO) is authorized to act as agent for the: North Atiantic Energy Corporation, Canal Electric Company, The Connecticut Light and Power Company, EUA Power Corporation, Hudson Light and Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, The United Illuminating Company, and Vermont Electric Generation and Transmission Cooperative, Inc.,

and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

930902011e 930816 DR ADOCK 0500 3

! l 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-86 is hereby amended to read as follows:

(2) Technical Soecifications i

TheTechnicalSpecificppionscontainedinAppendixA,asrevised through Amendment No.

and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No.

i NPF-86. NAESCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

\\/

JohnfF.Stolz, Director)

Profect Directorate I-V

.i M' ision of Reactor Projects - I/II 1

Office of Nuclear Reactor Regulation j

Attachment:

Changes to the Technical Specifications i

Date of Issuance: August 16, 1993 1

1 I

I 2

e t

s ATTACHMENT TO LICENSE AMENDMENT NO. 22 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of Appendix A, Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Overleaf pages have been provided.

Remove Insert xiii*

xiii*

xiv xiv 3/4 3-55 3/4 3-55 3/4 3-56*

3/4 3-56*

3/4 3-59*

3/4 3-59' 3/4 3-60 3/4 3-60 i

3/4 11-3*

3/4 11-4 3/4 11-4 3/4 12-l*

3/4 12-l*

I

'/4 12-2 3/4 12-2 i

1-3 3/4 12-3 3/4 12-4*

3/4 12-4*

)

6-17 6-17 6-18 6-18 6-21 6-21 6-22 6-22 t

6-23 6-23

O INDEX

5. 0 DESIGN FEATURES SECTION PAGE 5.3 REACTOR CORE 5.3.1 FHEL ASSEMBLIES...........

5.3.2 CONTROL ROD ASSEMBLIES....................................

5-9 5-9

5. 4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE...........................

5-9 5.4.2 VOLUME.

5-9

5. 5 METEOROLOGICAL TOWER LOCATION..............................

5-9

5. 6 FUEL STORAGE 5.6.1 CRITICALITY.....................

5.6.2 DRAINAGE....................................................

5-10 5-10

5. 6. 3 CAPACITY............................

5-10

5. 7 COMPONENT CYCLIC OR TRANSIEN1 LIMIT...........................

5-10 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENTLIMITS..................

5-11 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY........................

6-1 6.2 ORGANIZATION................................................

6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS..........................

6-1 6.2.2 STATION STAFF.............................................

6-2 FIGURE 6.2-1 (This figure number is not used)...................

6-3 FIGURE 6.2-2 (This figure number is not used)...................

6-3 TABLE 6.2-1 MINIMUM Shirt r%EW COMPOSIT10H......................

6-4 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

Function...............................

6-5 Composition...............................................

6-5 Responsibilities.........................

6-5 Records......................................

6-5 6.2.4 SHIFT TECHNICAL ADVIS0R...................................

6-5 6.3 TRAINING....................................................

6-5 4

SEABROOK - UNIT 1 xiii

l i

INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION 11G1 1:

6.4 REVIEW AND AUDIT......................

6-6 6.4.1 STATION OPERATION REVIEW COMMITTEE (SORC)

Function........................

6-6 Composition 6-6 Alternates.......................

6-6 Meeting Frequency 6-6 Quorum........................

6-6 Responsibilities....

6-6 Records 6-8 6.4.2 NUCLEAR SAFETY AUDIT REVIEW COMMITTEE (NSARC)

Function........................

6-8 Composition 6-8 Alternates.......................

6-8 Consultants 6-8 Meeting Frequency 6-9 t

Quorum.........................

6-9 Review.........................

6-9 Audits.........................

6-9 t

Records 6-11 6.5 ' REPORTABLE EVENT ACTION 6-11 6.6 SAFETY LIMIT VIOLATION...............

6-11 6.7 PROCEDURES AND PROGRAMS 6-12 6.8 REPORTING RE0VIREMENTS 6.8.1 ROUTINE REPORTS 644 Startup Report.....................

6-14 Annu al Re p o r t s.....................

6-15 Annual Radiological Environmental Operating Report...

6-15 Annual Radioactive Effluent Release Report.......

6-17 l

Monthly Operating Reports 6-18 CORE OPERATING LIMITS REPORT..............

6-18 6.8.2 SPECIAL REPORTS 6-19 (20 RECORD RETENTION......................

6-19 1

6.lc RADIATION PROTECTION PROGRAM 6-20 r

SEAE

- UNIT 1 xiv Amendment No. 9. 22

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INSTRUMENTATION MONITORING INSTRUMENTATION j

RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION l

I 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The Alarm /

Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (00CM).

APPLICABILITY:

At all times.

ACTION:

With a radioactive liquid effluent monitoring instrumentation a.

i channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to Specification 6.8.1.4 why this inoperability was not corrected in a timely manner.

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE RE0VIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-5.

l i

SEABROOK - UNIT 1 3/4 3-55 Amendment No. 22

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l l

TABLE 3.3-12 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

o8 75 MINIMUM

'e CHANNELS si INSTRUMENT OPERABLE ACTION 1.

Radioactivity Monitors Providing Alarm and e,

Automatic fermination of Release a.

Liquid Radwaste Test Tank Discharge 1

29 b.

Steam Generator Blowdown Flash Tank Drain 1*

30 c.

Turbine Building Sumps Effluent Line 1

30 2.

Flow Rate Measurement Devices E

a.

Liquid Radwaste Test Tank Discharge 1

31 4

ER b.

Steam Generator Blowdown Flash Tank Drain la 31 c.

Circulating Water Discharge 1**

N A.

J.

Radioactivity Monitors Providing Alarm but Not Termination of Release a.

Primary Component Cooling Water System (In lieu of 1

32 service water monitors) 4.

Rate of Change Konitor Primary Component Cooling Water System Head Tank 1

33 a.

(In lieu of service water monitors)

0nly applicable when steam generator blowdown is directed to the discharge transition structure.

- Pump performance curves generated in place should be used to estimate flow.

4

TABLE 4.3-5 (Continued)

TABLE NOTATIONS (1)

The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the normal or surveillance test Alarm / Trip Setpoint.

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

(4)

CHANNEL CHECK shall consist of verifying indication of tank level during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SEABROOK - UNIT 1 3/4 3-59 kmendnent No. J, 22 007 1 0 581

E INSTF"ENTATION MONI~ 4ING INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1

3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are nr r exceeded.

The Alarm / Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCH.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, b.

With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Annual Radioactive Effluent l

Release Report pursuant to Specification 6.8.1.4 why this inoperability was not corrected in a timely manner.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel thall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6.

I 3/4 3-60 Amendment No. 22 SEABpnnK - UNIT 1

RADI0 ACTIVE EFFLUENTS LIQUID EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERABLE and appropri-ate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each enit, to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY:

At all times.

ACTION:

With radioactive liquid waste being discharged without treatment and a.

in excess of the above limits and any portion of the Liquid Radwaste i

Treatment System which could reduce the radioactive liquid waste dis-charged not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that includes the following information:

1 1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

i b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Ocses due to liquid releases from each unit to UNRESTRICTED AREAS I

shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

1 4.1L 1. 3. 2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

SEABROOK - UNIT 1 3/4 11-3

m i

j RADIOACTIVE EFFLUENTS LIOVID EFFLUENTS LIOVID HOLDVP TANKS

LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each temporary unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive terial in any temporary unprotected outdoor tank exceedin' he above limit. immediately suspend all additions of radioact..a material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.8.1.4.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.1.4 The quantity of radioactive material contained in each temporary unprotected outdoor tank shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 day-when radioactive materials are being added to the tank.

P

Tanks included in this specificati tre those outdoor tanks that are not surrounded by liners, dikes, or we capable of holding the tank contents and that do not have tank overfic and surrouncing area drains connected to the Liquid Radwaste Treatment _, stem.

t SEABROOK - UNIT 1 3/4 11-4 Amendment No. 22

3/4.12 RADIOLOGICAL ERVIRONMENTAL MONITORING 3/4.

MONITORING PROGRAM LIMITING CONDITION FOR OPERATION l

3.12.1 The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in the ODCH.

APPLICABILITY:

At all times.

ACTION:

With the Radiological Environmental Monitoring Program not being a.

conducted as specified, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.8.1.3, a description of the reasons for not conducting i

the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of the REMP wnen averaged over any calendar quarter, prepare and submit to the Commission within 30 days from receipt of the laboratory analyses, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, or 3.11.2.3.

When more than one of the radio-nuclides in the REMP are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

+ * * * > 1. 0 reporting level (1) + reporting level (2)

When radionuclides other than those listed in the REMP are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

to a MEMBER OF THE PUBLIC from all radionuclides is equal to ar greater than the calendar year limits of Specification 3.11.1.2, 3.11.2.2, or 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 Annuel Radiological Environmental Operating Report required by Specification 6.8.1.3.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

SEABROOK - UNIT 1 3/4 12-1

RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 (Continued)

ACTION:

c.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by the Radiological Environ-mental Monitoring Program (REMP), identify specific locations for obtaining replacement samples and add them withir. 30 days to the REMP given in the ODCM.

The specific locations from which samp'as were unavailable may th.

be deleted from the monitoring progra-Pursuant to Specificati.

6.13, submit in the next Annual Radioau-tive Effluent Release Re ort documentation for a change in the OCCM including a revised figure (s) and table for the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

d.

The provisions of Specification 3.0.3 are not applicable.

SVRVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to the REMP from the ecific locations given in the table and fig-ure(s) in the ODCM, and shall analyzed oursuant to the requirements of and the detection capabilities rec.

~ed by the REMP.

SEABRDOK - UNIT 1 3/4 12-2 Amendment No.22

l -,

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 dis-tance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest mi the nearest residence, and the nearest garden

of greaterthan50m]kanimal#

(500 ft ) 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, pursuant to Specification 6.8.1.4, identify the new location (s) in the next Annual Radioactive Effluent Release Report.

b.

With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM, if permission from the owner to collect samples can be obtained and sufficient sample volume is available. 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.

Pursuant to Specification 6.13, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting 1

the change in sampling locations, c.

The provisions of Specification 3.0.3 are not applicable.

Broad leaf vegetation sampling of at least three different kinds at vegetation may be performed at the SITE BOUNDARY in each of two different direction sec-tors with the highest predicted relative deposition values (D/Qs) in lieu of I

the garden census.

Specifications for broad leaf vegetation sampling in the REMP, shall be followed, including analysis of control samples.

SEABROOK - UNIT 1 3/4 12-3 Amendment No. 22 i

l RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS SURVEILLANCE R;4UIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using a method such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities, as described in the ODCM.

The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.8.1.3.

A SEABROOK - UNIT 1 3/4 12-4

1 l.

ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l-6.8.1.4 A routine Annual Radioactive Effluent Release Report covering the operation of the station during the previous calendar year of operation shall be submitted by May 1 of each year.

The Annual Radioactive Effluent Release Reports shall include a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the station as outlined in Regulatory Guide 1.21, " Measuring, 4

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

For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61),

type of container (e.g., LOA, Type A, Type B, large Quantity) and SOLIDIFICATION agent or absorbent (e.g., cement).

The Annual Radioactive Effluent Release Report shall include an annual sumary of hourly meteorological data collected over the previous year. This annual sumary may be either in the form of an hour-by-hour listing on 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 l

assessment of the radiation doses due to the radioactive liquid and gaseous effluents released fro.n the unit or station during the previous calendar year.

This same report shall also include an assessment of the radiation doses from l

l radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their i

activities inside the SITE B0UNDARY (Figure 5.1-3) during the report period.

l All assumptions used in making these assessments, i.e., specific activity, exposure timt and location, shall be included in these reports. The l

meteorologica conditions concurrent with the time of release of radioactive i

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 methodology and parameters in the 0FFSITE DOSE CALCULATION MANUAL (0DCM).

The Annual Radioactive Effluent Release Report 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 l

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

SEABROOK - UNIT 1 6-17 Amendment No. 22

ADMINISTRATIVE CONTROLS ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 (Continued) 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 Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of adioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and the ODCM, pursuant to Specifications 6.12 and 6.13, respectively, as well as any major change te Liquid. Gaseous, or Solid Radwaste Treatment Systems pursuant to Specification 6.14.

It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Specification 3.12.2.

The Annual Radioactive Effluent Release Report shall also include the following:

an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Specification 3.3.3.9 or 3.3.3.10, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively.

MONTHLY OPERATING REPORTS 6.8.1.5 Ro-1e reports of operating statistics and shut sn experience shall be submittec.n a monthly basis to the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attn: Document Control Desk, with a copy to the NRC Regional Administrator, no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.8.1.6.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

1.

SHUTDOWN MARGIN limit for MODES 1, 2, 3, and 4 for Specification 3.1.1.1, 2.

SHUTDOWN MARGIN limit for MODE 5 for Specification 3.1.1.2, 3.

Moderatcr Temperature Coefficient BOL and E0L limits, and 300 ppm surveillance limit for Specification 3.1.1.3, t

SEABR M - UNIT 1 6-18 Amendment No. N, 22,

b ADMINISTRATIVE CONTROLS l

HIGH RADIATION AREA 6.11.1 (Continued) 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 that continuously indicates the radiation dose rate in the area; or l

l b.

A radiation monitoring device that 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 established and personnel have been made knowledgeable of them; or I

c.

An individual 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 l

specified in the Radiation Work Permit.

6.11.2 In addition to the requirements of Specification 6.11.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface that the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals 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 made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.12 PROCESS CONTROL PROGRAM (PCP) 6.12.1 The PCP shall be approved by the Commission prior to implementation.

6.12.2 Licensee-initiated changes to the PCP:

a.

Shall be submitted to the Commission in the Annual Radioactive l

Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

SEABROOK - UNIT 1 6-21 Amendment No. 22

I ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (PCP) t 6.12.2 (Continued) 1)

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; 2)

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3)

Documentation of the fact that the change has been reviewed and found acceptable by the 50RC.

5.

Shall become effective upon review and acceptance by the 50RC.

6.13 FFSITE DOSE CALCULATION MANUAL (0DCM) 6.13.1 The OCDM shall be approved by the Commission prior to implementation.

6.13.2 Licensee-initiated changes to the ODCH:

a.

Changes to Part A shall be submitted to and approved by the NRC staff prior to implementation.

1 b.

Changes to Part B shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:

4 1)

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 00CM to be changed with each page numbered, dated and containing the revision number, together with appr)priate analyses or evaluations justifying the change (s);

2)

A determination that the change will not reduce the accuracy i

or reliability of dose calculations or Setpoint determinations; and 3)

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

c.

Changes to Part B shall become effective upon review and a ceptance by the SORC.

SEABROOK - UNIT 1 6-22 Amendment No. 22

l ADMINISTRATIVE CONTROLS 6.14 MAJOR CHANGES TO LIOUID. GASE0US. AND SOLID RADWASTE TREATMENT SYSTEMS

6.14.1 Licensee-initiated major changes to the Radwaste Treatment Systems (liquid, gaseous, and solid):

a.

Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the 50RC.

The discussion of each change shall contain:

1)

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; 2)

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; 3)

A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; 4)

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; 5)

An evaluation of the change, which shows the expected maximum l

exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto 1

l 6)

A comparison of the predicted releases of radioactive materials, ir liquid and gaseous effluents and in solid waste, to tb?.ccual releases for the period prior to when the char.ge is ~o be made; 7)

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

8)

Documentation of the fact that the change was reviewed and found acceptable by the 50RC.

b.

Shall become effective upon review and acceptance by the SORC.

l

Licensees may choose to submit the information called for in this Specification as part of the annual FSAR update.

SEABROOK - UNIT 1 6-23 Amendment No. 22

.

ML20056G136

Text

Attachment:

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