ML20072Q722

Amend 116 to License NPF-12,changing TS to Permit Submittal of Radioactive Effluent Release Rept on Annual Basis

ML20072Q722
Person / Time
Site:	Summer
Issue date:	09/06/1994
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20072Q725	List: ML20072Q722 ML20072Q736
References
NUDOCS 9409120192
Download: ML20072Q722 (22)

Text

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UNITED STATES i

NUCLEAR REGULATORY COMMISSION

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W ASHINGTON. D.C. 2055fH)o01 l

SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICt AUTHORITY DOCKET NO. 50-395 l

VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. I j

AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 116 License No. NPF-12 l

l 1.

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

A.

The application for amendment by South Carolina Electric & Gas

{

Company (the licensee), dated February 25, 1994, 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 i

forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the l

provisions of the Act, and the rules and regulations of the Comission; 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 l

have been satisfied.

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-12 is hereby amended to read as follows:

l 9409120192 940906 PDR ADOCK 05000395 P

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i (2)

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.116, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

l 3.

This amendment is effective as of its date of issuance and shall be l

implemented within 30 days of issuance.

i FOR THE NUCLEAR REGULATORY COMMISSION

~~

David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 6, 1994

ATTACHMENT TO LICENSE AMENDMENT NO.116 TO FACILITY OPERATING LICENSE NO NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are indicated by marginal lines.

Remove Paaes Insert Paaes 1-4' l-4 1-5 1-5 3/4 3-26 3/4 3-26 3/4 3-30 3/4 3-30 3/4 3-34 3/4-3-34 3/4 3-67 3/4 3-67 l

3/4~3-70 3/4 3-70 6-3 6-3 6-6 6-6 6-8 6-8 6-9 6-9 6-11 6-11 6-12 6-12 6-12a 6-12a 6-12b 6-12b 6-14 6-14 6-15 6-15 6-16 6-16 6-20 6-20 l

DEFINITIONS l

OFFSITE DOSE CALCULATION MANUAL (00CM) 1.17 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alars/ Trip Setpoints, and in the conduct of the

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Environmental Radiological Monitoring Program. The 00CM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by l

Specifications 6.9.1.6 and 6.9.1.8.

OPERABLE - OPERABILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing-its specified function (s),

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

OPERATIONAL MODE - MODE 1.19 AnOPERATIONALMODE(i.e., MODE)shallcorrespondtoanyoneinclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

PHYSICS TESTS 1.20 PHYSICS TESTS shall_be those tests perfomed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1)describedinChapter14.0oftheFSAR,2)authorizedundertheprovisions of10CFR50.59,or3)otherwiseapprovedbytheConnission.

PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.

PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes'wil be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71. State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

SulmER - UNIT 1 1-4 Amendment No. W,116

i-

!f' DEFINITIONS I

j PURGE - PURGING t

1.23 PURGE or PURGING is the controlled process of discharging air or gas i

from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

i j

00ADRANT POWER TILT RATIO

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2 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-i brated outputs, or the ratio of the maximum lower excore detector calibrated j

output to the average cf the lower excore detector calibrated outputs, whichever is greater. With one excore detector ino shall be used for computing the average. perable, the remaining three detectors j

RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer i

the reactor coolant of 2775 MWt.

8 l

REACTOR TRIP SYSTEM RESPONSE TIME f

l 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the tim when the monitored parameter exceeds its trip setpoint at the channel sensor j

until loss of stationary gripper coil voltage.

i j

REPORTABLE EVENT 1

i 1.27 A REPORTA8LE EVENT shall be any of those conditions specified in l

Section 50.73 to 10 CFR Part 50.

i SHUTDOWN MARGIN i.

j 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

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fully inserted except for the single rod cluster assembly of hghest reactivity worth which is assumed to be fully withdrawn.

1 l

SLAVE RELAY TEST 1,29 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay.

The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

j 1.30 Not Used W

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SOURCE CHECK 3

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

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SUt44ER - UNIT 1 1-5 Amendment iso. 77.g,116 4

v>

>8 TABLE 3.3-4 (Continued) i ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Ey Total Functional Unit Allowance (TA) Z S

Trip Setpoint Allowable Value c

1 3.

CONTAINMENT ISOLATION

a. Phase "A" Isolation i

1.

Manual NA NA NA NA NA 2.

Safety Injection See 1 above for all safety injection setpoints and allowable values 3.

Automatic Actuation Logic NA NA NA NA NA y

and Actuation Rele s Y'

b. Phase "B" Isolation 1.

Automatic Actuation MA NA NA NA NA Logic and Actuation Reles 2.

Reactor Building 3.0 0.71 1.5 512.05 psig

$12.31 psig Pressure-High 3

c. Purge and Exhaust Isolation i

1.

Safety Injection See.1 above for all safety injection setpoints and allowable values

?

2.

Containment Radioactivity NA NA NA High C

3.

Automatic Actuation NA NA NA NA NA i

Logic and Actuation Relays

• Trip setpoints shall be set to ensure that the limits of 00CM Specification 1.2.2.1 are not exceeded.

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INSTRUMENTATION i

j TABLE 3.3-5 (Continued) j i

j ENGINEERED SAFETY FEATURES RESPONSE TIMES i

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INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS i

i e.

Reactor Building Purge and Not Applicable

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Exhaust Isolation j

f.

Emergency Feedwater Pumps-Not Applicable g.

Service Water System 571.5(4)/81.5(5) h.

Reactor Building Cooling Units

$76.5(4)/86.5(5)

1..

Control Room Isolation Not Applicable a

l 3.

Pressurizer Prewm -:.nw a.

Safety b 'ection (ECCS) 527.0(2)/27.0(1) b.

Reactor TcIp (from SI) 53.0 j

c.

Feedwater *.olation

$10.0 i

d.

Containment Isolation -Phase "A"

<45.0(4)/55.0(5) e.

Reactor Building Purge and Not Applicable i

j Exhaust Isolation t

f.

Emergency Feedwater Pumps Not Applicable j

g.

Service Water System 571.5(4)/81.5(5)'

j h.

Reactor Building Cooling Units

$76.5(4)/86.5(5) i 1.

Control Room Isolation Not Applicable

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4.

Differential Pressure Between Steam Lines-High f

a.

SafetyInjection(ECCS) 527.0(2)/37.0(3)

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b.

Reactor Trip (from SI) 53.0 i

c.

Feedwater Isolation

$10.0 j

d.

Containment Isolation -Phase "A"

$45.0(4)/55.0(5) l i

i t

SUPMER - UNIT 1 3/4 3-30 Menkent No. $J,JM,116 i

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i INSTRUMENTATION 1

TABLE 3.3-5 (Continued) l TABLE NOTATION i.

(1)

Diesel generator starting and sequence loading delays from under voltage included. Response time limit includes positioning of valves j

to establish SI path and attainment of discharge pressure for i

centrifugal charging pumps and RHR pumps. Sequcntial transfer of l

centrifugal charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is not included.

l 1

(2)

Diesel generator starting delay ngt included. Sequence loading delay l.

1 included. Offsite power available. Response time limit includes positioning of valves to establish SI path and attainment of i

discharge pressure for centrifugal charging pumps. Sequential transfer of egntrifugal charging pump suction from the VCT to the RWST(RWSTvalvesopen,thenVCTvalvesclose)isincluded.

)

l (3)

Diesel generator starting and sequence loading delays from under l

voltage included. Response time limit includes positioning of valves j

to establish SI path and attainment of discharge pressure for centrifugal charging pumps. Sequential transfer of centrifugal charging pump suction from the VCT to the RWST (RWST valves open, l

then the VCT valves close) is included.

l (4)

Diesel generator starting delay _ng), included. Sequence loading delay i

included. Offsite power available..

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(5)

Diesel generator starting and sequence loading delays from j

undervoltage included.

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i Sul01ER - UNIT 1 3/4 3-34 Amendment No. 198,116 i.

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INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION I

l LIMITING CONDITION FOR OPERATION 3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alare/ trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

l APPLICABILITY: As shown in Table 3.3-13 ACTION:

With an explosive gas monitoring instrumentation channel alarm / trip

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a.

setpoint less conservative than required by the above Specification, declare the channel inoperable and take the ACTION shown in Table l

3.3-13.

b.

With less than the minimum number of explosive gas monitoring l

instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to operable status i

within 30 days and, if unsuccessful prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

The provisions of Specifications 3.0.3 and 3.0.4 are rot applicable.

l c.

1 l

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each explosive gas monitoring instrumentation channel shall be l

demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION l

and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-9.

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i SUP94ER - UNIT 1 3/4 3-67 Amendment No. 35,704,116

un i

i Ey TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL MODES IN WHICH CHANNEL CHANNEL OPERATIONAL SURVEILLANCE INSTRIMENT CHECK CALIBRATION TEST REQUIRED 1.

WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.

Hydrogen Monitor D

Q(1)

M b.

Oxygen Monitor D

Q(2)

M O

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E.

2 a

E LE L

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ADMINISTRATIVE CONTROLS ~

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6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of a multi-disciplined dedicated onsite group with a minimum assigned complement of five engineers or appropriate specialists.

RESPONSIBILITIES.

6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification

• that these activities are performed correctly and that human errors are reduced as much as practical.

AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for procedure revisions, equiperat modifications, maintenance activities.. operations activities or other means of improving plant safety to the General Manager, Nuclear Safety.

6.2~.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

6.3 UNI'. STAFF OUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the members of the Independent Safety Engineering Group, each of whom shall have a Bachelor of Science degree or registered Professional Engineer and at least two years experience in their field. At least one year experience shall be in the nuclear field.

6.4 NOT USED l

• Not responsible for sign-off function.

SUMER - UNIT 1 6-3 Amendment No. 78,56,79,106,116 I

, - - = _. -. -.

ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The Plant Safety Review Comittee shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activ-ities performed under the responsibility.and authority provisions of these technical specifications. Copies shall be provided to the Vice President, Nuclear Operations, and the Chairman of the Nuclear Safety Review Committee.

6.5.2 NUCLEAR SAFETY REVIEW COMITTEE (NSRC)

FUNCTION 6.5.2.1 The Nuclear Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:

a.

nuclear power plant operations b.

nuclear engineering c.

chemistry and radiochensitry d.

metallurgy e.

instrumentation and control f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices COMPOSITION 6.5.2.2 NSRC shall consist of a Chairman and four or more other members appointed by the Vice President, Nuclear Operations. No more than a minority l

of the members of the NSRC shall have line responsibility for the operation of the unit.

The NSRC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la through h.

In the aggregate, the membership of the comittee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the Vice President, l Nuclear Operations; however, no more than two alternates shall participate as voting members in NSRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the kiRC Chairman to provide expert advice to the NSRC.

SUMER - UNIT 1 6-6 Amendment No. 18,79,116

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l ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 The NSRC shall have cognizance of the sudits listed below. Audits may l

be perfomed by using established SCE&G groups such as the ISEG and QA or by outside groups as determined by the NSRC. Audit reports or suumarits will be-i I

the basis for NSRC action:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions.

l b.

The performance, training and qualifications of the entire unit staff.

l The results of actions taken to correct deficiencies occurring in c.

unit equipment, structures, systems or method of operation that affect nuclear safety.

l d.

The perfomance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50.

l e.

The Emergency Plan and implementing procedures.

l i

f.

The Security Plan and implementing procedures.

[,

g.

Any other area of unit operation considered rp ropriate by the NSRC or the Vice President, Nuclear Operations.

l h.

The Fire Protection Program and implementing procedures.

l ;

i.

An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or a qualified outside firm.

j.

An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

k.

The radiological environmental monitoring program and the results thereof, including the performance of activities required by the quality assurance program per R.G. 4.15 Rev. 1. February 1979.

l 1.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.

l m.

The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes.

l AUTHORITY 6.5.2.9 The NSRC shall report to and advise the Vice President, Nuclear l

Operations, on those areas of responsibility specified in Sections 6.5.2.7 and 1

6.5.2.8.

SUPMER - UNIT 1 6-8 Amendment No. 78,/2,/9,116 i

j

ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of NSRC activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of each NSRC meeting shall be prepared, approved and forwarded to the Vice President, Nuclear Operations, within 14 days following l

each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be pre-pared, approved and forwarded to the Vice President, Nuclear Operations, within 14 days following completion of the review.

c.

Audit summary reports encompassed by Section 6.5.2.8 above, shall be forwarded to the NSRC and the Vice President, Nuclear Operations.

l Full audits shall be forwarded to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a.

Procedures required by Technical Specification 6.8 and other proce-dures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change. Procedures other than Administrative Procedures will be approved as delineated in writing by the General Manager, Nuclear Plant Operations. The General Manager, Nuclear Plant Operations will approve administrative procedures, security implementing procedures, and emergency plan implementing procedures. Temporary approval to procedures which clearly do not change the intent of the approved procedures can be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License.

For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedures shall approve the change.

b.

Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the General Manager, Nuclear Plant Operations. Each such modifica-tion shall be designed as authorized by Engineering Services and shall be reviewed by an individual / group other then the individual /

group which designed the modification, but who may uc from the same organization as the individual / group which designed the modifications.

Implementation of modifications to plant nuclear safety-related structures, systems and components shall be concurred in by the General Manager, Nuclear Plant Operations.

Sul9iER - UNIT 1 6-9 Amendment No. 35,79,116 l.

ADMINISTRATIVE CONTROLS d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

The applicable procedures recomended in Appendix "A" of Regulatory a.

Guide 1.33, Revision 2 February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety-related equipment.

d.

Security Plan.

e.

Emergency Plan.

f.

Fire Protection Program.

g.

PROCESS CONTROL PROGRAM.

h.

OFFSITE DOSE CALCULATION MANUAL.

1.

Effluent and environmental monitoring program using the guidance in Regulatory Guide 4.15. Revision 1. February 1979.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed

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prior to implementation as set forth in 6.5 above.

6.8.3 NOT USED.

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l 6.8.4 The following programs shall be established, implemented and maintained:

i 3

l a.

Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of sys%ss outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the chemical and volume contrc1, letdown, safety injection, residual heat removal, nuclear sampling, liquid radwaste handling, gas radwaste handling and reactor building spray system.

The program shall include the following:

i (1) Preventive maintenance and periodic visual inspection requirements, and (ii)

Integrated leak test requirements for each system at refueling cycle intervals or less.

b.

In-Plant Radiation Monitorina (1

Training of personnel, (11 Procedures for monitoring, and (iii Provisions for maintenance of sampling and analysis equipment.

SUMiER - UNIT 1 6-11 Amendment No. 78,49J2,1),116

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ADMINISTRATIVE CONTROLS

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i c.

Secondary Water Chemistry

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A program for monitoring of secondary water chemistry to inhibit i

steam generator tube degradation. This program shall include:

(i)

Identification of a sampling schedule for the critical variables j

and control points for these variables.

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)

(ii)

Identification of the procedures used to measure the values of the critical variables.

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(iii) i Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser j

in-leakage,

)i (iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for all off-control point chemistry conditions, i

i (vi) A procedure identifying (a) the a'uthority responsible for the i

interpretation of the data, and (b) the sequence and timing of j

administrative events required to initiate corrective action.

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d.

Postaccident Samplina j

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A program which will ensure the capability to obtain and analyte i

reactor coolant, radioactive iodines and particulates in plant i

gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the following:

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(i Training personnel, (11 Procedures for sampling and analysis, (iii Provisions for maintenance of sampling and analysis equipment.

t

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e.

Radioactive Effluent Controls Procram i

j j

A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to i

members of the public from radioactive effluents as low as reasonably i

achievable. The program (1) shell be contained in the 00CM, (2) shall l

1 be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

4, 4

1)

Limitations on the operability of radioactive liquid and gaseous i

monitoring instrumentation including surveillance tests and setpoint determinations in accordance with the methodology in

{

the ODCM, t'

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2)

Limitations on the concentration of radioactive material 4

released in liquid effluents to unrestricted areas conforming to

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10 CFR Part 20, Appendix B. Table II, Column 2; 1

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SUMER - UNIT 1 6-12 Amendment No.

D,

ADMINISTRATIVE CONTROLS Radioactive Effluent Controls Procram (Continued) e.

3)

Monitoring, sampling, and analysis of radioactive liquid and gcscous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the 00CM; 4)

Limitations on the annual and quarterly doses or dose comitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas conforming to Appendix I to 10 CFR Part 50; 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the 00CM at least every 31 days; 6)

Limitations on the operability and use of,the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases or radioactivity when the projected doses ir. m 31-day period would exceed 2 percent of the guidelines for t h snnual or dose commitment conforming to Appendix I to 10 UR Part 50; 7)

Limitations on the dose rate resulting from radioactive material released in gaseous affluents to areas beyond the site boundary conforming to the doses associated with 10 CFR Part'20 Appendix B. Table II, Column 1; 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50; 9)

Limitations on the annual and quarterly doses to a member of the public from Iodine-131 Iodine-133, tritium, and all radionuclides in particulate from with half-lives greater than 8 days in gaseous effluents released to areas beyond the site boundary confoming to Appendix I to 10 CFR Part 50; 10)

Limitations on the annual dose or dose comitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f.

Radiolooical Environmental Monitorina Procram A program shall be provided to monitor th'e radiation and radionuclides in the environs of the plant. The program shall provide (1)representativemeasuresofradioactivityinthe l

highestpotentialexposurepathways,and(2)verificationofthe accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) confom to the guidance of Appendix I to 10 CFR Part l

50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM; Sul#4ER - UNIT 1 6-12a Amendment No. 1 8,116

ADMINISTRATIVE CONTROLS C

f.

Radiolooical Environmental Monitorino Procram (Continued) l, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of the census; and 3)

Participation in an Inter-laboratory Comparison Program to ensure that independent checks on the precision and accuracy of measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring..

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i SUMMER - UNIT 1 6-12b Amendment No. 10#,116 l

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t l~l' ADMINISTRATIVE CONTROLS This report shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of specification 3.4.8.

The following information shall be included:

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

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The annual radiological environmental operating report covering the-operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.8.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

6.9.1.7 Not used.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Annual radioactive effluent release report covering the operation of the unit during the previous 12 months of operations shall be submitted within 60 days after January 1 of each year.

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

SUMER - UNIT 1 6-14 Amendment No. D, W,116

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i SUMAER - UNIT 1 6-15 Amendment No.

79,7g4, l

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ADMINISTRATIVE CONTROLS 6.9.1.9 Not used.

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, in-cluding documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly ba:is to the Director, Office of Resource Management, U.S. Nuclear Regulatory Connission, Washington, D.C.

20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.

A report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted as set forth in 6.5 above.

CORE OPERATING LIMITS REPORT 6.9.1.11 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:

Moderator Temperature Coefficient BOL and E0L Limits and 300 ppe a.

surveillance limit for Specification 3/4.1.1.3, b.

Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, Control Rod Insertion Limits for Specification 3/4.1.3.6, c.

d.

Axial Flux Difference Limits, target band, and APLND for Specification 3/4.2.1, RTP ND Heat Flux Hot Channel Factor, Fq,K(Z),W(Z),APL andW(Z)BL e.

for Specification 3/4.2.2, i

RTP f.

Nuclear Enthalpy Rise Hot Channel Factor, FaH, and Power Factor Multiplier, PFaH. limits for Specification 3/4.2.3.

j The analytical methods used to determine the core operating limits shall be j-those previously reviewed and approved by the NRC, specifically those described in the following documents:

WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"

a.

July 1985 (W Proprietary).

I SUMER - UNIT 1 6-16 Amendment No. 19,gg,J M,116

ADMINISTRATIVE CONTROLS 4

6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) i e

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6.14.1 The 00CM shall be approved by the Consission prior to implementation.

6.14.2 Changes to the ODCM:

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

retained as required by Specification 6.10.2.o.

This documentation shall contain:

1)

Sufficient information to support the change together with appropriateanalysesorevaluationsjustifyingthechange(s);

3 and 2)

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR I

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

b.

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

j Shall be submitted to the Consission in the fom of a complete c.

1egible copy of the entire 00CM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the l

s report in which any change to the 00CM was made. Each change sha'11 be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

SUM 4ER - UNIT 1 6-20 Amendment No. $1,79.J04,116