ML20205E992

Proposed Tech Specs,Changing Corporate Organizations That Provide Support to Nuclear Safety & Revising Shift Crew Personnel Complement for Compliance w/10CFR50.54(m)(2)(i)

ML20205E992
Person / Time
Site:	Rancho Seco
Issue date:	08/12/1986
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20205E985	List: ML20205E979 ML20205E992
References
TAC-60162, NUDOCS 8608190058
Download: ML20205E992 (17)

Text

. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF FIGURES (Continued)

Figure 3.5.2-7 ' Core Imbalance vs. Power Level, 0 to 40 EFPD 3.5.2-8 Core Imbalance vs. Power Level, after 30 EFPD 3.5.2-9 Core Imbalance vs. Power Level, af ter 300 EFPD with APSRs Withdrawn 3.5.2-10 Deleted 3.5.2-11 Deleted 3.5.2-12 Deleted 3.5.4-1 Incore Instrumentation Specification Axial Imbalance Indication 3.5.4-2 Incore Instrumentation Specification Radial Flux Tilt Indication 3.5.4-3 Incore Instrumentation Specification 3.18-1 General Layout of Site 4.13-1 Main Steam Inservice Inspection 4.13-2 Main Feedwater Inservice Inspection l 4.13-3 Main Steam Dump Inservice Inspection 138>< 6.2-1 SMUD Corporate Support of Nuclear Safety to Rancho Seco 6.2-2 Plant Organization Chart Proposed Amendment No. 138, Rev. 1 xii e e60812 kDR IOgyK05000312 P

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, RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 138>> Administrative Controls 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 138> 6.1.1 The Manager, Nuclear Plant shall be responsible for the management of the overall facility and shall delegate in writing the succession to

< his responsibility during his absence.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for the facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be composed of at least the minti..#0 shift crew composition shown in Table 6.2-1.

b. At least one licensed Operator shall be in the control room when fuel is in the reactor,

c. At least two licensed Operators shall be present in the control

room during reactor start-up, scheduled reactor shutdown and l during recovery from reactor trips.

136> d. An individual qualified in radiation protection practices and

< procedures shall be on site when fuel is in the reactor.

e. ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to Fuel Handling who has no other concurrent responsibilities during this operation.

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f. A site Fire Brigade of at least 5 members shall be maintained onsite at all times.* The Fire Brigade shall not include 3 members of the minimum shif t crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

• Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

Proposed Amendment No. 138, Rev. 1 6-1 l

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, RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.2 ORGANIZATION FACILITY STAFF

g. Administrative procedures shall be developed and implemented to limit the working hours of facility staff who perform safety-related functions; e.g., senior reactor operators, 138>< reactor operators, radiation protection personnel, auxiliary operators, and key maintenance personnel.

Adequate shif t coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require-substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

a. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time,

b. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.

c. A break of at least eight hours should be allowed between work periods, including shift turnover time,

d. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shif t.

Any deviation from the above guidelines shall be authorized by 138>< the Manager, Nuclear Plant or his designee, or higher levels of management, ii. accordance with established procedures and with documentation of the basis for granting the deviation. Controls 138> shall be included in the procedures such that individual overtime shall be reviewed monthly by the Manager, Nuclear Plant

< or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

Proposed Amendment No. 138, Rev. 1 6-la

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls TABLE 6.2-1 138>< SHIFT CREW PERSONNEL AND LICENSE REQUIREMENTS

• REACTOR MODE COLD OTHER THAN RANCHO SEC0 JOB TITLE SHUTDOWN COLD SHUTDOWN Shift Supervisor 1-SL 1-SL 138> Asst. Shift Supervisor or Control Room Operator 2-L 1-SL, 2-L Auxiliary Operator or Equipment Attendant 2 2 Equipment Attendant or

< Power Plant Helper 3 3 Shift Technical Advisor 0 1 138>< Minimum Total Personnel 8 10 138><

• In the event that any member of a minimum shift crew is absent or incapacitated due to illness or injury, a qualified replacement shall be designated to report on site within two hours.

SL - NRC Senior Licensed Operator L - NRC Licensed Operator Proposed Amendment No.138, Rev.1 6-2

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1 Ra:icho Seco Unit 1

[kJure 6.2- 1 Technicol Specifications Administr ative U.ontrols f SMUD CORPORATE SUPPORT I i 0F NUCLEAR SAFETY TO I RANCHO SECO j Board of i

Directors i

General Personnel Manager l Management safety i

I Review Committee l

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, Deputy Deputy **

General Manager General Manager Utility Operations Nuclear I

AGM" Nuclear Nuclear Administration & Projects Plant Services Nuclear Nuclear

- Security Training Engineering

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Purchases & Nuclear Nuclear Stores Quality -

Licensing 1 - Corporate changes may be made per 10 CFR S0.59 Nuclear Emerg.

withour prior NRC approval. -

Preperedness AGl1--Assistant General tlanager

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• Responsible for Fire Protection Pr ogram Proposed Amengment No.138, Rev.1 6-2a

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I Figure 6.2-2 Rancho Seco Unit 1 Admisinstrative Conti ob i

Technical Specifications PLANT ORGANIZATION CilART l Manager Nuclear Plant Asst. Manager l Staff Assistant i i l l Radialion Nuclear Nuclear Nuclear

• Nuclear Protection -

Maintenance Operations Technical Scheduling Superintendent Manager Manager Manager Manager immmmmmmmmmma -

Mechanical Regulatory Operations

• Compliance

- Maintenance - -

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! 1 - Organization changes may be Electrical Fire incident i made per 10 CFR 50.59 with- -- Maintenance Protection Analysis out prior NRC approval.

• - Shift Operations Supt. shall be a Senior Licensed Operator.

Inst. & Control Chemistry Technical

- Maintenance - -

Support I i

- FacHities Nuclear l llP Support and Environ. Program j Proposed Amendment No.138, Rev.1 6-2b ,

TECHNICAL SPECIFICATIONS Administrative Controls 6.3 FACILITY 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 N 138>< for (1) the Radiation Protection Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shif t Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline. The STA shall receive specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the operating staff 138> shall be maintained under the direction of the Manager, Nuclear 4 Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR, Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the 138>< direction of the Manager, Nuclear Training and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except refresher classroom training shall be on a quarterly schedule.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)

FUNCTION 138> 6.5.1.1 The Plant Review Committee shall function to advise the Manager,

< Nuclear Plant on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review Committee shall be composed of the:

138> Assistant Manager, Nuclear Plant Chairman Nuclear Technical Manager Alternate Chairman / Member Nuclear Maintenance Manager Member Nuclear Operations Manager Member Nuclear Scheduling Manager Member

< Radiation Protection Superintendent Member Proposed Amendment No. 138, Rev. 1 6-3 l

. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls ALTERNATES 6.5.1.3 A list of alternates for the chairman and members shall be developed 138>< and approved by the Manager, Nuclear Plant. However, no more than two alternates shall participate in PRC activities at any one time for the purposes of establishing a quorum.

138> SUBCOMMITTEES 6.5.1.4 Subcommittees and qualified reviewers shall be utilized as determined

< by the PRC Chairman to provide support to the PRC.

MEETING FREQUENCY 138>< 6.5.1.5 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman.

QUORUM 138>< 6.5.1.6 A Quorum of the PRC shall consist of the Chairman and three members including alternates.

RESPONSIBILITIES 138>< 6.5.1.7 The Plant Review Committee shall be responsible for:

138> a. Review of the required safety analysis of 1) all procedures required by Specification 6.8 and changes thereto, and 2) any other proposed procedures or changes thereto as determined by

< the Manager, Nuclear Plant to affect nuclear safety.

138>< b. Review of the safety analyses of all proposed tests and experiments that affect nuclear safety.

138> c. Review of all proposed changes to the Technical Specifications or the Operating License.

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

138> e. Review of all violations of the Technical Specifications.

f. Review of all Licensee Event Reports.

< g. Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Management Safety Review Committee.

Proposed Amendment No.138, Rev.1 6-4

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls RESPONSIBILITIES (Continued) 138> h. Review of the Plant Security Plan and changes thereto,

i. Review of the Emergency Plan and changes thereto.

j. Changes to the Process Control Program and the Offsite Dose Calculation Manual. (See Specifications 6.15 and 6.16.)

k. Major changes to the Radioactive Waste Treatment Systems (Liquid,

< Gaseous and Solid). (See Specification 6.17.)

AUTHORITY 138>< 6.5.1.8 The Plant Review Committee shall:

138> a. Recommend to the Manager, Nuclear Plant written approval or

< disapproval of items considered under 6.5.1.7(a) through (k) above.

b. Render determinations in writing with regard to whether or not 138,< each item considered under 6.5.1.7(a) through (e) above constitutes an unreviewed safety question.

c. Provide immediate written notification to the Chairman of the Management Safety Review Committee of disagreement between the 138>< PRC and the Manager, Nuclear Plant; however, the Manager, Nuclear Plant shall have responsibility for resolution of such disagreements pursuant to 6.5.1.1 above.

RECORDS 138> 6.5.1.9 The Plant Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Manager, Nuclear

< Plant and the Chairman of the Management Safety Review Committee.

I Proposed Amendment No. 138, Rev. 1 6-5 1

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RANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 138> . 6.5.2 Management Safety Review Committee (MSRC)

FUNCTION 6.5.2.1 The MSRC shall report to and advise the General Manager on those areas specified in Section 6.5.2.7.

COMPOSITION 6.5.2.2 The MSRC shall be composed of the:

Manager, Nuclear Projects Chairman Manager, Corporate Quality Alternate Chairman /

Member Manager, Nuclear Engineering Member Manager, Nuclear Plant Member Manager, Licensing Member Manager, Nuclear Training Member Consultant (Operational Utility Background) Member Consultant (Nuclear Engineering or Health Member

< Physics background)

ALTERNATES 6.5.2.3 A current list of alternates approved by the General Manager shall be maintained by MSRC Secretary. In case of the absence of both the Chairman and the Alternate Chairman as provided in 6.5.2.2, a

Temporary Alternate Chairman may be designated, in writing, by the General Manager. No more than two alternates shall participate in 138> MSRC activities at any one time for the purposes of establishing a

< quorum.

CONSULTANTS i

138> 6.5.2.4 Consultants shall be utilized as determined by the MSRC Chairman to

< provide expert advice to the MSRC.

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! Proposed Amendment No. 138, Rev. 1 6-6 i

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS l

Administrative Controls 138> 6.5.2.5 MEETING FREQUENCY

< The MSRC shall meet at least once per calendar quarter.

QUORUM 6.5.2.6 A quorum of MSRC shall consist of the Chairman or alternate and four (4) members or their alternates. The majority of the voting quorum must be members of the MSRC.

REVIEW 6.5.2.7 The MSRC shall review:

138>< a. The safety analysis 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.

138> d. Proposed changes in Technical Specifications or this Operating License.

e. Violations having nuclear safety significance of applicable statutes, codes, regulations, orders, Technical Specifications,

< license requirements.

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

Proposed Amendment No. 138, Rev. 1 6-7

.~ RANCHO SECO UNIT 1 TECHNICAL' SPECIFICATIONS Administrative Controls 138>< g. Licensee Event Reports as defined by 10CFR50.73 and NUREG 1022.

h. Any indication of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.

i. Reports and meeting minutes of the Plant Review Committee.

138>- j. Plant Security Plan changes.

k. Rancho Seco Emergency Plan changes.

1. The Offsite. Dose Calculation Manual changes.

m. QA Program.

n. Oversight Review of the QA Audit Program.

l, RECORDS 6.5.2.8 Records of MSRC activities shall be prepared, approved, and distributed as indicated below:

l a. Minutes of each MSRC meeting shall be prepared, approved, and l forwarded to the Deputy General Manager - Nuclear and the General Manager.

b. Documentation of reviews emcompassed by Section 6.5.2.7 e, f, g,

and h above, shall be prepared, approved and forwarded to the Deputy General Manager - Nuclear and the General Manager.

6.5.3 TECHNICAL REVIEW AND CONTROL l

- Activities which affect nuclear safety shall be conducted as follows:

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a. Procedures required by Technical Specification 6.8 and other procedures 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 (s) other than the individual (s) which prepared the i procedure or procedure change, but who may be from the same l organization as the individual (s) which prepared the procedure or procedure change. Procedures will be approved as delineated L in writing by the Hanager, Nuclear Plant. The Manager, Nuclear

-< Plant will approve Security Plan Implementing Procedures and Proposed Amendment No.138, Rev.1 6-8 l

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RANCHO SECO UNIT 1

. TECHNICAL SPECIFICATIONS

. Administrative Controls -

138> a. (Continued)

Emergency Plan Implementing Procedures. Temporary approval of procedure changes 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 (s) authorized.by the Manager, Nuclear Plant above to approve the procedure 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 Manager, Nuclear Plant. Each such modification shall be designed as authorized by Nuclear ~

Engineering and shall be reviewed by an individual (s) other than the individual (s) who designed the modification, but who may be from the same organization as the individual (s) who I designed the modifications.

c. Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Updated Safety Analysis Report shall be reviewed by an individual (s) other than the individual (s) who prepared the proposed test or experiment.

d. Events reportable pursuant to the Technical Specification 6.9 and violations of Technical Specifications shall be

! investigated and a report prepared which evaluates the event

! and which provides recommendations to prevent recurrence. Such report shall be reviewed by the PRC and fowarded to the i

Manager, Nuclear Plant and forwarded to the Chairman of the

Management Safety Review Committee.

e. Individuals responsible for reviews performed in accordance i with 6.5.3.a. 6.5.3.b and 6.5.3.c shall meet or exceed the qualification requirements of Section 4.4 of ANSI 18.1, 1971.

i Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the review I personnel of the appropriate discipline.

AUDITS 6.5.4 Audits of facility activities shall be performed under the cognizance of the Manager, Nuclear Quality.- These audits shall encompass:

a. The conformance of facility operation to all provisions contained within the Technical Specifications and applicable

< license conditions at least once per year.

Proposed Amendment No. 138, Rev. 1 6-9

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 138> 6.5.4 b. . The performance, training and qualifications of the District's 4 entire facility. technical staff at least once per year.

c. The result of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or methods of operation that affect nuclear safety at least once per six months.

d. The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two (2) years,

e. The Facility Emergency Plan and implementing procedures at least once per two (2) years.

f. The Facility Security Plan and implementing procedures at least once per two (2) years.

g. Any other area of facility operation considered appropriate by 138>< the MSRC, Deputy General Manager - Nuclear or the General Manager.

h. Compliance with fire protection requirements and implementing procedures at least once per two (2) years.

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

j. An inspection and audit of the fire protection and loss prevention program shall be perfonned by an outside qualified fire consultant at intervals no greater than three (3) years,

k. The radiological environmental monitoring program and the results thereof at least once per 12 months.

1. The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures-at least once per 24 months.

m. The PROCESS CONTROL PROGRAM for the SOLIDIFICATION of radioactive wastes from liquid systems at least once per 24 months.

138> n. Reports of reviews encompassed by Section 6.5.2.7 (except e, f, g, and h) forwarded to the General Manager and to the

< management positions responsible for the areas reviewed.

Proposed Amendment No. 138, Rev. 1 6-10

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. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 138> 6.6 LICENSEE EVENT REPORT ACTION 6.6.1 The following actions shall be taken for events which are reportable as LICENSEE EVENT REPORTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10CFR50, and

b. Each LICENSEE EVENT REPORT shall be reviewed by the PRC and the

< results of this review submitted to the MSRC.

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l Proposed Amendment No. 138, Rev. 1 6-10a i

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36 (c) (1) (1) shall be complied with immediately.

138> b. The Safety Limit violation shall be reported to the Nuclear Operations Manager, the Manager, Nuclear Plant, the Chairman of

< the MSRC and to the Commission immediately.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC. 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 138> Commission, the MSRC, and the Manager, Nuclear Plant, within 10

< days of the violation.

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

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Procedures implementation.

g. Process control program implementation.

h. Offsite Dose Calculation Manual implementation.

i. Effluent and environmental quality control program.

138> 6.8.2 Each procedure of 6.8.1 above and changes thereto shall be reviewed and approved as set for.th in Specification 6.5. Such procedures shall

< be reviewed periodically in accordance with administrative procedures.

Proposed Amendment No. 138, Rev. 1 6-11

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.. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.3.1 . Continued)

The radioactive effluent release reports shall include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the site-boundary during the report period. All assumptions used in making these assessments (e.g.,

specific activity, exposure time, and location) shall be included in these reports.

The radioactive effluent release reports shall include the following information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:

a. A description of the event and equipment involved.

b. Cause(s) for the unplanned release.

c. Actions taken to prevent recurrence.

d. Consequences of the unplanned release.

The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents

! released from the unit during each calendar quarter, as outline in i Regulatory Guide 1.21. The releases of effluents shall be used for i determining the gaseous pathway doses. The assessment of radiation

} doses shall be. performed in accordance with the Offsite Dose l Calculation Manual (0DCM).

The radioactive effluent release reports shall include any changes to i the PROCESS CONTROL PROGRAM (PCP) or (0DCM) made during the reporting l- period, as provided in Specifications 6.14 and 6.15.

MONTHLY REPORT l

i 6.9.3 Routine reports of operating statistics, including narrative summary

( of operating and shutdown experience, of lif ts of the Primary System l Safety Valves or EMOVs, of major safety related maintenance, and j tabulations of facility changes, tests or experiments required l pursuant to 10 CFR 50.59(b), shall be submitted on a monthly basis to l 138x the Director of Inspection and Enforcement, U. S. Nuclear Regulatory

! Commission, Washington, D. C. 20555, with a copy to the Regional l Office, postmarked no later than the 15th day of each month following j the calendar month covered by the report, LICENSEE EVENT REPORT f-l 6.9.4 The LICENSEE EVENT REPORTS of Specification 6.9.4.1 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC as Licensee Event Reports. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a License Event Report shall be completed and reference shall be made to the original report l date, pursuant to the requirements of 10 CFR 50.73.

Proposed Amendment No. 138, Rev. 1 6-12c i