ML20002A939

From kanterella
Jump to navigation Jump to search
Tech Spec Change Amending Apps a & B to OL Re Administrative Controls
ML20002A939
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 12/03/1980
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20002A938 List:
References
NUDOCS 8012090212
Download: ML20002A939 (25)
v • d • e


Text

. _ _ _ _ ._ _ __ _ . _ ._ - ._ __ .. > . __

o

. 4

%)'

?

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE T

6.1 RESPONSIBILITY ..................... 6-1 6.2 ORGANIZATION ~ ......................

j Offsite.. . . . . . . . . . . . . . . . .-. . . . . . . . 6-2 Facility Staff 6-2 L .....................

4 1

< 6.3 FACILITY STAFF QUALIFICATIONS ............. 6-3 t

i 6.4 TRAINING ....-.................... 6-3 6.5 REVIEW AND AUDIT . . . . . . . . . . . . . . . . . . . . .

l 6.5.1 PLANT REVIEW C&lMITTEE Function ........................ 6-4 l Com ;n s i t ion .' . . . . . . . . . . . . . . . . . . . . . . 6-4 1

J- Alternates ....................... 6-4 ,

l j Meeting Frequenc y . . . . . . . . . . . . . . . . . . . . 6-4 Quorum .......................... 6-4 1 Responsibilities .................... 6-4 1

a 1 Authority .-. . . . . . . . . . . . . . . . . . . . . . . 6-5 4

d Records . . . . . . . . . . . . . . . . . . . . .... (wf 1

j 6.5.2 NUCLEAR GENERAL REVIEW COMMITTEE 4

[ Function. . . . . . . . . . . . . . . . . . . . . . . . . 6 .

j Com ;n s i t i on . . . . . . . . . . . . . . . . . . . . . . . ~6-7 I Qualifications. . . . , . . . . . . . . . . . . . . . . . 6-S

Alternates. . . . . . . . . . . . . . . . . . . . . . . . 6-8 Consultants . . . . . . . . .-. . . . . . . . . . . . . 6-9 1
CRYSTAL RIVER. - UNIT 3 .XV .

1

. _18 012090$4. .

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE Meeting Frequency . . . . . . . . . . . . . . . . . . . . 6-8 Quorum . . . . .. . . . . ............... 6-8 Review .. . . . . . . . . ............... 6-9 Audits . . . . . . . . . . ............... 6-9 Authority . . . . . . . . . . . . . . . . . . . . . . . 6-10 Records . . . . . . . . . . . . . . . . . . . . . . . . . 6-10 6.6 REPORTABLE OCCURRENCE ACTION .............. 6-11 6.7 SAFETY LIMIT VIOLATION . . . .............. 6-11 6.8 PROCEDURES . . .. . . . . . .............. 6-11 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE AND REPORTABLE OCCURRENCES ........... 6-13 Startup Report .. . . . . ............... 6-13 Annual Rep 3rts .. . . . . ............... 6-13 Monthly Operating Report . ............... 6-14 Reportable Occurrences . . ............... 6-14 Prompt Notification with Written Follow-up ....... 6-15 Thirty Day Written Rep,rts ............... 6-1t 6.9.2 SPECIAL REPORTS . . . . . . ............... 6-17 6.10 RECORD RETENTION .. . . . . .............. 6-17 6.11 RADIATION PROTECTION PROGRAM ,............. 6-19 i 6.12 HIGH RADIATION AREA . .. . ....... ...... 6-19 CRYSTAL RIVER - UNIT 3 XVI

~- . . .- ~ . . - _ - . .-. - - - . . . - _- . - - ..

Y TECHNICAL SPECIFICATION CHANGE REQUEST NO. 67'(APPENDICES A AND B)

L Delete.and add the following pages in Appendices A and .B -

Delete Add Appendix A 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4' 6-5 6-5' 4

6-6 6-6*

6-7 6-7 6-8 6-8 6-9 6-9 6-10 6 ! 6-11 6-11'

! 6-12 6-12* '

6-13 6-13 6-14 6-14 '

6-15 6-15

'6-16 6-16 6-17 6-17 6-18 6-18

. 6-19 6-19 Appendix B 5-5 5-5' 5-Sa* ,a 5

' Denotes pages containing proposed changes.- All other pages are provided as i

5 a result of carryover:and retyping.

Proposed Change 11 The changes proposed will alter current on-site administrative controls in tun major areas:

l (1) The PRC composition is expanded to provide additional members from several plant deparbnents.

4 (2) The procedure review process is expanded to provide an alternate review process not including the PRC in pre-implanentation~ review of.

l certain procedures.

Reason for Proposed Change

. The. expanded PRC will allow several improvements in our conduct of business at i

the plant site. The'improvoments will have a positive effect on plant safety by allowing: necessary review functions to go on concurrent with other

~

~

4 L

i

~ +-

-., -- n s , - -

-e - - , s , - - , , , - - - , v- - -

activitics. Th se improvanents includs, but are not limited to:

-(a) The Technical Assistant to the Nuclear Plant Manager should be the

~

primary general advisor to the manager and most properly should 3erve as chairman of the PRC. This will allow a more proper belancing of the interests of various plant departments.

(b) By expanding participation in the PRC greater specific expertise / interest can be directed toward reviews.

(c) By expanding number of members it is more likely that representatives from all departments can participate in all meetings.

(d) By expanding number of members greater continuity will exist as personnel transfer, promote, etc.

(e) By expanding number of members general point of view, policy, etc. is less likely to be affected by absence of particular members /deparbnents.

The augmented review process will provide the following improvanents:

(a) By having clearer line responsibility, reviews are more likely to be thorough and accurate.

(b) The actual individuals working on a problem will have the most current expertise on various issues. They will also be most able to identify proper reviewers in interfacing departments.

(c) The Qualified Reviewers in each department will develop a broad understanding of the impact of various procedures on other departments.

(d) Less PRC time will be taken-up in routine activities.

(e) Important management time will not be diverted from primary roles.

Safety-Cost / Benefit Analysis Justifying Proposed Change Florida Power considers the preceding to have clearly underscored the benefits of the proposed change. The following potential drawbacks were also considered :

(1) PRC expansion could lower the level of review (less " management" involvement) FPC does not consider this to outweigh the benefits since a more deliberate review by roughly equally experienced personnel is superior to overburdening a relatively few key personnel.

,(2) Revised review process could lessen quality of review. FPC considers this highly unlikely. Superintendent level approval and 50.59 review by PRC is required to assure necessary management involvement. By placing more responsibility on those doing " detail" work quality is expected to improve.

Florida Power is strongly convinced that in light of current interest in "Hunan Factors" the proposed change is a step toward a more efficient and thorough onsite review process. Diversion of senior site management to review functions does not support their main function and in fact could divert their attention from important matters. The ability to operate the plant in a safe man.... is expected to be significantly enhanced by this change.

i 9 , , rmt-- us-

6.0 - ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Nuclear Plant Manager shall be responsible for overall facil-ity operation and shall delegate in writing the succession to this re-sponsibility during his absence.

6.1.? The Nuclear Plant Manager shall be responsible for an annual fire protection inspection which shall be performed utilizing either quali-fied offsite licensee personnel or an outside fire protection firm. The inspection shall consist of: a) an inspection of safety-related areas of the Plant to verify that they are in conformance with the fire hazards analysis; and b) a review of the Fire Brigade organization, training, and drills to verify their conformance with the requirements of Sec-tion 27 of the NFPA Code-1976.

6.1.3 The Nuclear Plant Manager shall be responsible for an inspection of the fire protection program to be performed by a qualified outside fire consultant at least once per 36 months.

i i

l CRYSTAL RIVER - UNIT 3 6-1

r ,

ADMINISTRATIVE CONTROLS-l 6.2 ORGANIZATIONL

^

OFFSITE 6.2.1 - The offsite organization for 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 shif t shall be composed of at least the minimun

- 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 Con-trol Room during reactor start-up, scheduled reactor shutdown, and during recovery from reactor trips.
d. An individual qualified' in radiation protection 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 Opera-tor or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f. A site Fire Brigade of at least 5 members shall be maintained on-site at all times.# The Fire Brigade shall not include 5 members of the minimum shift crew. necessary for safe shut-down of the unit and any personnel required for other essen-tial functions during a fire emergency.
  1. Fire Brigade composition.may be less than the minimum requirements for a period of time not .to exceed 2-hours in order to accommodate unexpect-ed absence of Fire Brigade members provided innediate action is taken to restore the Fire Brigade .to within the minimum requirements.

CRYSTAL RIVER - UNIT 3' 6-2 M T- T

_~

s .

. ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the mini-mum qualifications of ANSI N18,1-1971 for comparable positions, except for the Chemistry and Radiation Protection Engineer who shall meet or exceed the qualifications of Regulatory Guide ~ 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Plant Mana-ger 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 direction of the Nuclear Plant Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976, except for Fire Bri-gade training sessions which shall be held at least quarterly.

CRYSTAL RIVER - UNIl 3 6-3 1

i

[

4 ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)

FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the Nuclear Plent Manager on all matters related to nuclear safety.

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

Chairman: Technical Assistant to the Nuclear Plant Manager Member: Technical Services Superintendent or Reactor Specialist Member: Operations Superintendent or Operations Engineer Member: Technical Support Engineer or Performance Engineer

, Supervisor '

Member: Maintenance Superintendent or Maintenance Staff Engineer Member: Chemistry and Radiation Protection Manager or Chemistry and Radiation Protection Specialist Member: At large (Designated by Chairman)

ALTERNATES 6.5.1.3 Ai1 alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basis; no more than two alternates shall participate as voting members in PRC activities at any one time.

QUORUM 6.5.1.5 A quorum of the PRC shall consist of the Chairman or his desig-nated alternate and four members including alternates.

RESPONSIBILITIE5 6.5.1.6 The Plant Review Committee shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Nuclear Plant Manager to affect nuclear safety.
b. Review of all proposed tests and experiments that affect nuclear safety.
c. Review of all proposed changes to the Appendix "A" Technical Specifications.

, CRYSTAL RIVER - UNIT 3 6-4 9

1 l

i ADMINISTRATIVE CONTR1LS RESPONSIBILITIES (Continued)

d. Review' of all proposed changes or modifications to plant sys-tems or equipment that affect nuclear safety.
e. Investigation'. of all violations of the Technical Specifica-tions including the preparation and forwarding.of reports cov-ering evaluation and recommendations to prevent recurrence to t he Assi stant Vice President, Nuclear Operations, and the Chairman of the Nuclear- General Review Committee.
f. . Review of events requiring 24-hour written notification to the Commission.
g. Review of facili ty operations to detect potential nuclear safety hazards.

. h. Performance of special reviews, investig6 cions or analyses, and reports thereon, as requested by the Chairman of the Nuclear General Review Committee.

i. Review of the Plant Security Plan and shall submit recommended changes to the Gnairman of the Nuclear General Review Committee.

J. Review of the Emergency. Plan and shall submit recommended changes to the Chairman of- the Nuclear General Review Commit'ae.

AUTHORITY 6.5.1.7 The Plant Review Committee shall:

a. Recommend to the Nuclear Plant Manager written approval or disapproval of items considered under 6.5.1.6.(a) through (d) above.
b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above con-

-stitutes an unreviewed safety question,

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Assistant Vice President, Nuclear Operations, and to the Chairraan of- the Nuclear -General Review Commir . of disagreement between the PRC and the Nuclear Plant !4pt or; however, the Nuclear Plant

~

Manager shall . have resp to it tP ~ / far resolution of such disa-greements pursuant to b !.1 J c t.

CRYSTAL RIVER - UNIT 3 6-5

l ADMINISTRATIVE CONTROLS RECORDS ,

6.5.1.8 The Plant Review Committee shall maintain written minutes of each meeting and copies shall be ~ provided to the Assistant Vice Presi-dent, Nuclear Operations, and - Chairman of the Nuclear General Review Committee.

e 1

CRYSTAL RIVER - UNIT 3 .6-6 i

_~_.___--__----_.__.--___:-_.____ . _ . - _ _ - . _ _ - . _ _ _ L__._._-..'__-____---___.-_-___:__.______-__

ADMINISTRATIVE CONTROLS 6.5.2 NUCLEAR GENERAL REVIEW COMMITTEE (NGRC)

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

a. Nuclear- pmver plant operations.
b. Nuclear engineering-
c. Chemistry and radiochemistry
d. Metallurgy
e. Instrumentation and control
f. Radiological safety
g. Mechanical and electrical engineering
h. Quality assurance practices COMPOSITION 6.5.2.2 The NGRC shall be composed of the Chairman, Vice Chairman, and at least 5 members. No more than a minority of the members shall have line responsibility for operation of the facility. The Committee shall, collectively, have the experience and competence required to review problems in the following areas:
a. Nuclear power plant operations
b. Nuclear engineering
c. Chemistry and radiochemistry
d. Metal lurgy.
e. Nondestructive testing
f. Instrumentation and control
g. Radiological safety
h. Mechanical and electrical engineering
i. -Administrative-controls CRYSTAL RIVER UNIT:3 6-7

ADMINISTRATIVE CONTROLS COMPOSITION (Continued)

'.j Environmental

k. Quality assurance practices QUALII. CATIONS
.5.2.3 The following minimum experience requirements shall be. estab-

)ilshed for those persons involved in the independent offsite safety re-view and audit program:

a. Chairman and Vice-Chairman - Bachelor of Science in engineerinc or related field and ten years - related experience, including five_ years involvement with operation and/or design of nuclear power plants.
b. Pbmber - Bachelor of Science in engineering or related field and five years related experience including three years in-volvement with operation and/or design of nuclear power plants.

ALTERNATES 6.5.2.4 All alternate members shall be appointed in writing by the NGRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NGRC activities at any one time.

CONSULTANTS 6.5.2.5 Consultants shall be utilized' as detennined by the NGRC Chair-man to provide expert advice to the NGRC.

MEETING FREQUENCY 6.5.2.6 The NGRC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least .once per six. months thereaf ter. ,

QUORUM 6.5.2.7 ' A quorum of NGRC shall consist of the Chairman or his designat-  ;

ed alternate and five additional NGRC members, including alternates. No more than_ a minority of the quorum shall have line responsibility for l operation of the facility. H CRYSTAL RIVER ' UNIT 3 6-8 R a

ADMINISTRATIVE CONTROLS REVIEW 6.5.2.8 The NGRC shall review:

a. The safety evaluations for 1) changes to procedures, equip-ment, 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 i_nvolve .an unreviewed safety question as defi ned in Sec-tion 50.59, 10 CFR.

.c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes in Technical Specifications or this Operating License.
e. Violations of codes, regulation . rders, Technical Specifica-tions, license requirements, or c internal procedures or in-structions having nuclear safety significance.
f. Significant operating abnonnalities or deviations from nomal and expected perfonnance of plant equipment that affect nuclear safety.
g. Events. requiri ng 24-hour written notification to the Commi ssion.
h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related struc-tures, systems, or conponents.
i. Reports and meetings minutes of the Plant Review Committee.

AUDITS 6.5.2.9 Audits of facility activities shall be perfonned under the cog-nizance of the NGRC. These audits shall encompass:

a. The confonnance of facility operation to provisions contained within- the Technical Specifications and applicable license.

conditions at least once per 12 months.

b. The perfonnance , training and . qualifications of the entire facility staf f at least- once per 12 months.

CRYSTAL RIVER - UNIT 3 6-9 t

e ADMINISTRATIVE CONTROLS AUDITS (Continued)-

c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of oper-ation that affect nuclear safety at least once. per 6 months.
d. The perfonnance of activities requi red by the Operational Quality Assurance Program to meet the criteri a of Appen-dix "B",10 CFR 50, at least once per 24 nonths.
e. The Fac1. i ty Emergency Plan and implementing procedures at least once per 24 months.
f. The Facility Security Plan and implementing procedures at least once per 24 months.
g. The Facility Fire Protection Program and implementing proce-dures at least once per 24 months.
h. Any other area of facility operation considered appropriate by the NGRC or the Senior Vice President, Engineering &

Construction.

AUTHORITY 6.5.2.10 The NGRC shall report to and advise the Senior Vice President, Engineering & Construction, on those areas of responsibility specified in Sections 6.5.2.8 and 6.5.2.9.

RECORDS 6.5.2.11 Records of NGRC activities shall be prepared, approved, and distributed 1as indicated below:

a. Minutes of each' NGRC meeting shall be prepared, approved, and

-fondarded to the Senior Vice President, Engineering & Con-struction within-14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.8 above, shall be prepared, approved, and fonvarded to the Senior Vice Presi-dent , - Engi neeri ng & Construction, within 14 days following conpletion of the review.
c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President, Engineering & Con-struction, and. to the management posi.tions responsible for the areas audited within 30 days af ter completion of the audit.

CRYSTAL-RIVER - UNIT 3 6-10 l

l

ADMINISTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION-6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The' Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

1 b .- Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PRC and _ submitted to the NGRC and the Assistant Vice President, Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION-6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The facility shall be placed in at least HOT STANDBY within one hour.
b. . The Safety Limit violatio n shall be reported to the Commis-sion, the Assistant Vice President, Nuclear 0 erations, and to the NGRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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 struc-tures, and 3)-corrective action taken to prevent recurrence.
d. The Safety Limit Violation Report shall be submitted Eto the Commission, the NGRC and the Assistant Vice President, Nuclear Operations, within 14 days of the violation.

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

a. The applicable procedures recommended in Appendix "A" of Regu-latory Guide 1.33, November 1972.
b. Refueling operati)ns, i
c. Surveillance and test actisities of _ safety 'related equipment. '
d. Security Plan implementation.

CRYSTAL _ RIVER - UNIT 3 6-11

. ADMINISTRATIVE CONTROLS e .' Emergency P1an implementation.

'f.. Fire Protection Program implementation.

6.8.2 - Each - procedure and administrative policy of 6.8.1 above, and changes thereto, shall be . reviewed and approved prior to implementation as follows:

a. The Emergency Plan, Security Plan, and Fire Protection Plan and ' the associated implementing procedures, Administrative Procedures, and those test procedures associated with plant modifications shall_ be reviewed and approved by the PRC and the~ Nuclear Plant Manager prior to implementation.
b. For ~all other procedures', the review cycle shall consist of:

an intradepartment review by a -Qualified Reviewer, an inter-disciplinary review by Qualified Reviewer (s) in interfacing departments, as specified in Administrative Procedures, and approval by the responsible Superintendent or Manager, as spe-cified by Administrative Procedures. The PRC shall then re-view the 10 CFR 50.59 checklist within 14 days of approval.

c. The training and qualification of Qualified. Reviewers shall be governed by Administrative Procedures, with final cartifica-tion by the Nuclear Plant Manager. Recertification will be required on a periodic basis and upon transfer between depart-ments. As a minimun, all Qualified Reviewers shall meet the requirements of ANSI N18.1-1971, Sections 4. 2, 4. 3, 4.4, or 4.6, or the equivalent.
d. Each procedure and administrative policy of 6.8.1 shall be re-viewed on a periodic basis as set forth in Administrative a

rocedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intenu of the. original procedure is not altered.

> b. The change is approved by two members of the plant management

. staff, at least one of whom holds a Senior Reactor Operator's License on the unit af fected.

c. The change is documented and subsequently reviewed and approved in accordance with the requirements' of Specification 6.8.2 within 14 days of implementation.

CRYSTAL RIVER:- UNIT _3 6-12

~ _ -

ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition -to the applicabl'e reporting requirements of Title _10, Code of Federal Regulatiors, the following reports shall be. submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORTS 6.9.1.1 A summary report of plant startep and power escalation testing will be submitted following: 1) receipt of an Operating License, 2) amendment to the license involving a planned increase in power level, .

3) installation of fuel that has a different design or has been manufac-tured by a different fuel supplier, and 4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the ~ operating ' conditions or characteristics obtained during the test program and a comparison of these values with design predictions and speci fications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details rec,uested in license conditions based on other commitments shall be included _in this report.

6.9.1.3 Startup reports shal1 be submitted within: 1) 90 days following completion of the startup test program, 2) 90 days following resumption or commencement of commercial power operation, or 3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e. , initial criticality, completion of startup test program, and resumption or commencement of commercial power -

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

ANNUAL REPORTSI /-

6.9.1.4 Annual reports covering the activities of the unit as described bel ow for the previous calendar year shall be submitsted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

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

CRYSTAL RIVER - UNIT 3 6-13 m

'ADMINISTRATIVEJCONTROLS-STARTUP REPORTS (Continued) 6.9.'. 5 Reports required on an annual' basis shall include:

i a. A tabulation of the number of station, ' utility, and other per-sonnel- (including contactors) receiving exposures greater'than 100 mrem /yr and their associated man-rem exposure-according to work and job functions /2 , e.g. , reactor operations and surveil-lance, inservice inspection, routine maintenance, special main-tenance (describe maintenance), waste processing, and refuel-ing. -The dose assignments to various duty functions may be es-timated based on pocket dosimeter, TLD, or film badge measure-ments. Small exposures totaling less than 20 percent of the individual total dose need not be accounted for. In the aggre-gate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

b. A list of the re ctor vessel material surveillance capsules in-stalled in the reactor at the end of the report period and a summary of any withdrawals or insertions of capsules during the report period.- In supplying this information, the ownership of each capsule shall be indicated, and the irradiation location in the vessel of each capsule' which was inserted during the re-port period shall be identified.

MONTHLY'0PERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown-experience shall be submitted on a monthly basis to the Director, Office of Mange-ment Information and Program Control, U.S. Nuclear Regulatory Commis-sion, Washington, DC 20555, with a copy to the Regional Office, submit-ted no later than ~ the 15th of each month following the calendar month covered by the report.

REPORTABLE OCCURRENCES 6.9.1.7 _'The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 bel ow, including corrctive actions and measures to prevent re-currence,- shall be reported to the NRC. Supplemental reports may be re-quired to fully describe final resolution - of occurrence. In case of corrected or. supplemental reports, a Licensee Event Report shall be con-pleted and reference shall be made to the original report date.

2

/ This~ tabulation supplements the requirements of 20.407 of 10 CFR

'Part 20.

CRYSTAL RIVER - UNIT 3 6-14

ADMINISTRATIVE CONTROLS PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP.

6.9.1.8 The types of events' listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director 1of the Regional Office, or his designate, no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall in-clude, as a minimum, a. completed copy of a Licensee Event Report form.

Information provided on the Licensee- Event Report form shall be supple-mented, a; needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Failure of the . reactor protection system, or other systems subject to limiting safety system settings, to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications, or failure to com-plete the required protective function.
b. Operation of ~ tha wiit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the Technical Specifications.
c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
d. Reactivity anomalies involving disagreen .1 with the predicted value of reactivity balance under steady-state conditions dur-ing power operation greater than or equal to 1% Ak/k; a calcu-lated reactivity balance indicating a shutdown margin less conservative than specified in the Technical Specifications; short-tem reactivity increases that correspond to a reactor startup rate of greater than 5.2 DPM or, of subcritical, an unplanned reactivity insertion of more than 0.5% Ak/k; or oc-currence of any unplanned criticality.
e. Failure or malfunction of one or more components which pre-vents or could prevent, by itself, the fulfillment of the functional requirements of system (s) required to cope with accidents analyzed in the SAR.
f. Personnel error or procedureal inadequacy which prevents or c.ould ' prevent , by itself, the fulfillment of the functional requirements of systems required to cope with accidents ana-lyzed in the SAR.

CRYSTAL RIVER . UNIT 3 6 15

=

ADMINISTRATIVE CONTROLS PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP'(Continued) 9 Conditions arising from natural or man-made events that, as a direct result of ~ tee event, require plant shutdown, operation of safety systems, _ cr other protective measures required by Technical Specifications.

h. Errors discovered in the transient or accident analyses, or ir, the methods used for such analyses as described in the Safety Analysis Report, or in the bases for the Technical Specifica-tions that have or could have permitted reactor. operation in a manner less conservative tLan assumed in the analysis.
i. Performance of structures, systems, or components that re-quires remedial action or corrective measures to prevent oper-ating in a manner less conservative than that assumed in the accident analyses in the Safety Analysis Report <n Technical Specifications bases; or discovery during plant lite of condi-tions not specifically considered in the Safety Analysis Re-port or Technical Specification that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

THIRTY-DAY WRITTEN REPORT 6.9.1.9 The types of events listed below shall be the subject of writ-ten reports to the Director of the Regional Office within 30 days ofoc-currence of the event. The written report shall include, as a minimum, a completed copy of a Licensee Event Report form. Information provided on the Licensee Event Report form shall be supplemented, as caeded, by additional narrative material to provide complete explanation .of the circumstances surrounding the event.

a. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the Technical Specifications, but which do not prevent the fulfillment of the functional requirements of af fected systems.
b. Conditions leading to operation in a degraded mode, penaitted by a limiting condition for operation, or plant shutdown re-quired by a limiting condition for operation.
c. Observed inadequacies in the implementation of administrative or. procedural controls which threaten to cause -reduction of degree of redondancy provided in reactor protection systems or-engineered safety feature systems.

CRYSTAL RIVER - UNIT 3 6-16 a

4 .

~

ADMINISTRATIVE CONTROLS THIRTI-DAY WRITTEN REPORT (Continued)

d. Abnormal degradation of systems other than -those specified in 6.9.1.8.c - above, designed to contain radioactive material re-sulting from the. fission process.

SPECIAL REPORTS 6.9.2 Special reports 'shall be submitted to the Director of the Office of Inspection and Enforcement, Region II, within the time period speci-fied .for each report. . These reports shall be submitted covering the ac-tivities' identified below, pursuant to the requirements of the applica-ble . reference specification:

4

a. ECCS Actuation, Specification 3.5.2 and 3.5.3.
b. Inoperable Seismic Monitoring Instrumentation, Specifica-tion 3.3.3.3.
c. Inoperable Meteorological Monitoring Instrumentation, Specifi-cation 3.3.3.4.
d. Seismic Event Analysis, Specification 4.3.3.3.2.
e. Inorerable Fire Detection Monitori g Instrumentation, Specifi-cation 3.3.3.7.
f. Inoperable Fire Suppression System, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, and 3.7.11.4.

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation maintenance activities, ins pections , repair and replacement of principal items of equipment related to nuclear safety.
b. Records and logs of. principal maintenance activities, inspec-tions, repair and replacement of principal items of equipment-related to nuclear safety.
c. All REPORTABLE OCCURRENCES submitted to the Commission.

.d. Records .of surveillance activities, inspections, and calibra-tions required by these Technical Specifications. l l

e. Recurds of reactor tests and experiments.
f. Records.of changes made to Operating Procedures.

CRYSTAL RIVER - UNIT 3 6-17

d ADMINISTRATIVE CONTROLS 6.10 ' RECORD RETENTION (Continued)

g. Records of radioactive shipments.
h. Records of sealed-sou. .e and fission detector leak tests and results. ((, ,
i. Records of annual physical inventory of all sealed-source ma-terial -of record.

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a.~ Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
c. Records of facility radiation and contamination surveys.
d. Records of radi ation exposure for all individuals entering radiation control areas.
e. Records of gaseous and liquid radioactive material released to the environs.
f. Records of transient or operational cycles for those facility components identified in Table 5.7-1.
g. Records of training and qualifications for current members of the plant staf f.
h. Records of inservice inspections -performed pursuant to these Technical Specifications.
i. Records of ' Quality Assurance activities required by the QA Manual.

J. Records of revicws performed for changes made to procedu'res or equipment, or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the PRC and the NGRC.

CRYSTAL RIVER - UNIT 3 6-18

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consis-tent with the requirements of 10 CFR Part 20 and shall be . approved ,

maintained, and adhered Eto for all operations involving personnel radia-tion exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or "alann signal" required by paragraph 20.203(c) (2) of 10 CFR 20:

A Pigh Radiation Area, in which the intensity of radiation is grea'.er .than 100 mrem /hr but less than 1000 mrem /hr, shall be barriceded. and conspicuously posted as a High Radiation Area, and entrance thereto shall be controlled by issuance of a Rad-iation Work Permit, and any individual or groups of individu-als permitted to enter such areas shall be provided with a radiation monitoring device- which continuously indicates the radiation dose rate in the area.

b. A High Radiation Area in which the intensity of rraiation is greater than 1000 mrem /hr shall be subject to tne provisions of 6.12.1.a above and, in addition, locked doors shall be pro-vided to prevent unauthorized entry into such areas. The keys shall ~ be maintained under the administrative control of tne-Health Physics Supervisor, with one key assigned to the La'dmin-istrative control of the Shift Supervisor on duty.

CRYSTAL RIVER - UNIT 3 6-19

5-5 5.4 ACTION .TO BE TAKEN IF ' LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4.1 Immediate remedial actions as permitted by these environmental technical -specifications shall be implemented until such time as the limiting condition for operation is met.

5.4.2 The occurrence shall be promptly reported to the Chairman of the Nuclear General-Review Committee and investigated as spe-cified in Section 5.3.

5.4.3- The Nuclear General Review Committee shall prepare and submit a report for each occurrence in accordance with Sec-tion 5.3.10.

5.4.4 The' Assistant Vice President, Nuclear Operations, shall report the occurrence top the NRC as specified in Section 5.6.2.

5.5 PROCEDURES 5.5.1 Explicit written procedures, including applicable check-off lists and -instructions, shall be prepared for implementation of the monitoring requirements described in Sections 2 and 3, approved as specified in Section 5.5.2, and adhered to for op-eration of all systems and components involved in carrying out the effluent release and environmental monitoring programs.

Procedures shall include sampling, instrument calibration, analysis, and action to be taken when limits are approached or exceeded. Calibration frequencies and standards for instruments used in performing ~ the measuremer.ts shall be included. These frequencies shall be determined fran experi-ence with similar instruments in similar environments and fran manufacturers' technical. manuals.

5.5.2 Each procedure in 5.5.1 above, and changes thereto, shall be reviewed and approved prior to implementation as follows:

a. Except as noted in b:
1. All procedures shall be subjected to a review by a-Quali fied Reviewer within the responsible depart-ment, interdisciplin6ry review by Qualified Review-ers within interfacing departments as specified in Administrative Procedures, and the responsible su-perintendent or Plant Manager' as specified in Admin-istrative Procedures.
2. The training and qualification of reviewers shall be governed by Administrative Procedures with final certification by the Nuclear Plant 'ianager.

Sa Recertification"will be required on a! periodic basis and 'upon transfer between departments. As a mini-mum, all Qualified Reviewers sh611 neet the require-ments of ~ ANSI. N 18.1-19'i, Section 4.2, 4.4, or 4.6, or the equivalent.

3. - All- procedure revision records, including the re-views required by 10 CFR 50.59, .shall be reviewed by the Plant Review Cc.nmittee within 14 days, and for-warded to the Nuclear General Review Committee.
b. Tempora y changes may be made to procedures required by Section 5.5.1 provided:

1.- The - intent of the. original preocedure is- not' altered.

2. The change is approved by two members of the Plant Staff, at least one of which holds a SR0 License.
3. The change is documented and reviewed per 5.5.2.a.3, above. .

l d

1 f

k

Retrieved from "https://kanterella.com/w/index.php?title=ML20002A939&oldid=2478358"