ML20210G431
| ML20210G431 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/27/1999 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20210G387 | List: |
| References | |
| NUDOCS 9908030096 | |
| Download: ML20210G431 (9) | |
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1 LAR 98-0011 'JNDEX Page 10 ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . . . . . . ................... 6-1
. 6.2 ORGANIZATION Offsite and Onsite Organizations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 Fac il i ty S taff. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-la Facility S taff O vertime. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4a 6.3 FACILITY STAFF OUALIFICATIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 6.4 D e 1e t ed 'Y. 'D .A.- YM. , T. M. , t_'
.................................................H 6.5 REVIEW AND AUDrr 6.5.1 STATION REVIEW BOARD Fu nc ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 i l
Composition. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ..... ........ 6-6 Altern ates. . . . . . . . . . . . . . . . . . . . . . . . . . . ... . ............ .... 6-6 Meeting Frequency . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 Q u o ru m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................ 6-6 Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 Au th o ri ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-8 Rec ord s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 6-8 6.5.2 COMPANY NUCLEAR REVIEW BOARD Fu ncti on . . . . . . . . . . . . . . . . . . . . . . . . .......... ........ . ..... 6-8 Composition . . . . . .. .. ................ ................ 6-9 ,
1 Altemates . . . . . . . . . . . . . . . . .................. ................. 6-9 i
Con sultants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 6-9 l
9900030096 990727 PDR ADOCK 05000346 f P PDR DAVIS-BESSE. UNIT 1 XV Amendment No. 38.135,
r LAR 98-0011 Page11 l ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Manager - Radiological Control who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents, and (3) the Manager -
Plant Operations whose requirement for a senior reactor operator license is as stated in Specification 6.2.2.g. !
6.4 Deleted TRAINING I
1 6.d 1 A re: raining and replace =nt : raining progra:n fc the faeility ::aff cha!! bc =intained under the dirce:ica cf the Manager Nuclear Trai?ng and cha!! =c: c eneced the require =nt and recc:n=ndations of Sectica 5.5 cf ANSI FIS.! 1971 and of 10 CFR 55.59.
6.4.2 D !cted 6.5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB) 1 J
FUNCTION 6.5.1.1 The Station Review Board (SRB) shall function to advise the Plant Manager on all matters related to nuclear safety.
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DAVIS-BESSE, UNIT 1 6-5 Amendment No. 9.37.39.98.106.135.
138,142,169,174, m
O
- LAR 98-0011 Page 12 ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the CNRB. _These audhs ardescriked in the USAR Chagg12 Quality Assurance Procram. Thesc audit; sha!! cacc:n; =;:
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DAVIS-BESSE, UNIT 1 6-11 Amendment No. 12,27,74,86,139,
l LAR 98-0011 ADMINISTRATIVE CONTROLS f0RINFORMATIONarIy l
~
l 6.7 SAFETY LIMIT VIOLATION OR PROTECTIVE 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. i
- b. The Safety Limit violation shall be reported to the NRC Operations Center by telephone as soon as possible and in all cases within one hour. In addition the Vice President, Nuclear and the CNRB shall be i notified 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 SRB. 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 Commission, the CNRB and.the Vice President, Nuclear within 14 days li of the violation.
6.7.2 The following actions shall be taken in the event the Protective Limit of Specification 2.1.2 is violated:
- a. The facility shall be placed in at least HOT STANDBY within one hour.
- b. The Protective Limit violation shall be reported to the NRC Operations Center by telephone as soon as possible and in all cases within one hour. In addition the Vice President, Nuclear and the CHRB 'shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. A Protective Limit Violation Report shall be prepared. The report shall be reviewed by the SRB. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) l corrective action taken to prevent recurrence.
- d. The Protective Limit Violation Report shall be submitted to the CNRB ,
and the Vice President, Nuclear within 14 days of the violation. l 6.8 PROCEDVRES AND PROGRAfg 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.
DAVIS-BESSE, UNIT 1 6-13 Amendment No.9, U ,
/J ,A6,SE,AA9,Mp ,189
LAR 98-0011 L Page 14 ADMINISTRATIVE CONTROLS b
l l , 6.8 PROCEDURES AND PROGRAMS (Continued)
- c. Surveillance and test activities of safety related equipment,
- d. Industrial Security Plant implementation.
- c. Davis-Besse Emergency Plan implementation.
- f. Fire Protection Program implementation.
- g. The radiological environmental monitoring program.
- h. The Process Control Program.
- i. Offsite Dose Calculation Manual implementation.
6.8.2 Each procedure of 6.8.1 al ove, and changes thereto, shall be reviewed and approved prior to implementation as set forth in 6.5.3 above.
6.8.3 (deleted) 6.8.4 The following programs shall be established, implemented and maintained:
- a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include makeup, letdown, seal injection, seal return, low pressure injection, containment spray, high pressure injection, waste gas, primary sampling and reactor coolant drain systems. The program shall include the following:
(i) Preventive maintenance and/or periodic visual inspection requirements, and ;
(ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
4
- b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
1 (i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.
DAVIS-BESSE, UNIT 1 6-14 Amendment No. 9,12,51,98,109,189, i i l l l.
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LAR 98-0011 l- Page 15 ADMINISTRATIVE CONTROLS -
i .
l SPECIAL REPORTS 1
l 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission in accordance with 10 CFR 50.4 within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specifications:
- a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.
- b. Deleted
- c. Deleted
- d. Deleted ,
l
- e. Deleted i i
l
- f. Deleted
- g. Inoperable Remote Shutdown System control circuit (s) or transfer switch (es) required for a serious control room or cable spreading room fire, Specification 33.3.5.2.
6.10 RECORD RETENTION Recordsafhcility activities shallbe retained as described in the USAR Chanter 17 Ogglity Assurance Program.
6.10.1 The fc!!: "ing :==& ha!! bc =:::=d f= : 1:=: Eve y =::
- a. Rec =& =d !cg: cf f=ility cp= :!= :cv=ing time in:= val at e=h pcvcc level.
- b. R==& =d !cg: cf pri=ip:1 =in === =ti"i i=, !=p=:ic=, = pair =d =p!=:==: cf pri=ip:1 i :=: cf equip ==: =h:cd ic nucler =f::y.
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- d. Rec =6 cf =rvei!!=ce =:i hi=, !=p=:ic= =d = lib =:!c= = qui =d by th=: T=hnical Sp=iS= tic =.
- c. Rec =& cf ch=gew;& te Op=ating Proced=es.
f Reccri cf =d!=c:!= :hipment:.
- g. R==6 cf = !:d ;c== =d Emica d ::::ct !=h :=:: =d ==hs.
h R=cri ef-annual phy !:a! in=n:=y cf ;!! = led === =:=ial of meerd.
DAVIS BESSE, UNIT 1 6-18 Amendment 9,12,65,86,106, 135,170,174,187,201, l
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LAR 98-0011 Page 16
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l DAVIS.BESSE, UNIT 1 6-19 Amendment No. 8,12, 86,94,170, Order dated Oct. 24,1980
1 o
- LAR 98-0011 Page 17 ADMINISTRATIVE CONTROLS 1 ,
6.14 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
- a. Shall be documented and records of reviews performed shall be retained as required by the USAR Chanter 17 Ouality Assurance Procram. by Specificden 6.10.2.p. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and 1
- 2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- b. Shall become effective after review and acceptance by the SRB and the approval of the Plant Manager.
l 6.15 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
1
- a. Shall be documented and records of reviews performed shall be retained as required by by the USAR Chanter 17 Ouality Assurance Procram m Specification 6.10.2.p. This documentation shall contain:
1
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106,40 CFR 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 SRB and the approval of the Plant Manager.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall 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.
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DAVIS-BESSE, UNIT 1 6-22 Amendment No. 86,170,184, a
e .
Docket Number 50-346 ' l 1
- License Number NPF-3 Serial Number 2607 Enclosure 2 COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY THE DAVIS-BESSE NUCLEAR POWER STATION (DBNPS) IN THIS DOCUMENT.
ANY OTHER ACTIONS DISCUSSED IN THIS SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY THE DBNPS. THEY ARE DESCRIBED ONLY FOR INFORMATION AND ARE NOT REGULATO'RY COMMITMENTS.
PLEASE NOTIFY THE MANAGER - REGULATORY AFFAIRS (419-321-8466) AT ;
THE DBNPS OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY l ASSOCIATED REGULATORY COMMITMENTS. l COMMITMENT DUE DATE j
- 1. Relocate TS 6.5.2.8 (Audits) and These changes are to be implemented l
6.10 Records Retention to the DBNPS within 120 days after NRC approval Updated Safety Analysis Report of the License Amendment, and no i Chapter 17 Quality Assurance Program. later than the removal of TS 6.5.2.8 !
and 6.10 from the TS.
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