ML20206U730
| ML20206U730 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/19/1999 |
| From: | Anthony Mendiola NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206U734 | List: |
| References | |
| NUDOCS 9905250319 | |
| Download: ML20206U730 (11) | |
Text
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l UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHtNGTON, D.C. 20566-4001 49***,+,o i
ElBSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 231 License No. NPF-3 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the FirstEnergy Nuclear Operating Company (the licensee) dated October 28,1998, as modified by letter dated March 19,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9905250319 990519 DR ADOCK 05000346 PDR
2-(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 231, are hereby incorporated in the license. FirstEnergy Nuclear Opersting Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 120 days after issuance.
FOR THE NUCLEAR EGULATORY COMMISSION V
/A ony J. Mendiola, Chief, Section 2
/
P oject Directorate ill ivision of Licensing Project Management
)
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of issuance: May 19, 1999 I
ATTACHMENT TO LICENSE AMENDMENT NO.231 FACILITY OPERATING LICENSE NO. NPF-3 i
DOCKET NO 50-346
)
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove J2sg(1 XVI XVI 6-7 6-7 6-14 6-14 6-14a 6-14a 6-19 6-19 6-20 6-20 6-20a 6-20b 6-22 6-22
- 7..
'O s
INDEX ADMINISTRATIVE CONTROLS t
SECTION PAGE Meeting Frequency.
6-9 Quorum 6-9 Review 6-10 Audits 6-11 Authority.
6-12 Records.
6-12 6.5.3 Technical Review and Control 6-12 6.6 REPORTABLE EVENT ACTION.
6-12a 6.7 SAFETY-LIMIT VIOLATION OR PROTECTIVE LIMIT VIOLATION 6-13 6.8 PROCEDURES AND PROGRAMS 6-13 6.9 REPGRTING REOUIREMENTS 6.9.1 Routine Reports 6-14c 6.9.2 Special Reports 6-18 6.10 RECORD RETENTION 6-18 6.11 DELETED l
i 6.12 HIGH RADIATION AREA 6-20 6.13 ENVIRONMENTAL OUALIFICATION 6-21 6.14 PROCESS CONTROL PROGRAM (PCP) 6-22 6.15 OFFSITE DOSE CALCULATION MANUAL'(ODCM) 6-22 DAVIS-BESSE, UNIT 1 XVI Amendment No. 38,135,170,189, 231 i
l
I ADMINISTRATIVE CONTROLS d.
Review of proposed tests or experiments determined to involve an unreviewed safety question as defined in 10 CFR 50.59.
e.
Review of reports of violations of codes, regulations, j
orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed to contain radioactive material.
f.
Review of all proposed changes to the Techcical Sp; -ifications or the Operating License.
4 g.
Deleted h.
Review of reports of significant operating abnorr.alities or deviations from normal and expected performance of plant equipment that affect plant safety,
- i. Review of changes to the Industrial Security Plan, the l
Security Training and Qualification Plan, and the Security Contingency Plan.
l
- j. Review of changes to the Davis-Besse Emergency Plan.
l k.
Review of items which may constitute potential nuclear safety hazards as identified during review of facility operations.
1.
Investigations or analyses of special subjects as l
requested by the Company Nuclear Review Board.
m.
Review of all REPORTABLE EVENTS.
1 n.
Review of all Safety Limit Violation Reports and Protective Limit Violation Reports (Section 6.7).
o.
Review of any unplanned, accidental or uncontrolled radioactive releases, evaluation of the event, ensurance that remedial action is identified to prevent recurrence, review of a report covering the evaluation and forwarding of the report to the Plant Manager and to the CNRB.
p.
Review of the changes to the OFFSITE DOSE CALCULATION MANUAL.
q.
Review of the changes to the PROCESS CONTROL PROGRAM.
r.
Review of the Annual Radiological Environmental Operating Report.
s.
Review of the Radioactive Effluent Release Report.
t.
Review of c.hanges to the Fire Protection Program.
l DAVIS-BESSE, UNIT 1 6-7 Amendment No. 27,86,93,98,109, 139,174,184,189,231
1 0
j ADMINISTRATIVE CONTROLS 6.8.4 (Continued) c.
Post-Accident Samolina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following:
(i)
Training of personnel, (ii)
Procedures for sampling and analysis, (iii)
Provisions for maintenance of sampling and analysis equipment.
d.
Radioactive Effluent Controls Procram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include i
the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM.
2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, sampling and analysis of radioactive Monitorink,gaseouseIfluentsinaccordancewith10 3) liquid an CFR 20.1302,and with the methodology and l
parameters in the ODCM.
4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in li@id effluents released from each unit 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 ODCM at least every 31 days.
DAVIS-BESSE, UNIT 1 6-14a Amendment No. 37,84,93,170, 231
1
- ~
ADMINISTRATIVE CONTROLS 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 modifications made to systems and equipment described in the Final Safety Analysis Report.
(
b.
Records of new and irradiated fuel inventory, fuel j
transfers and assembly burnup histories.
j c.
Records of radiation exposure for all individuals entering radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
Records of transient or operational cycles for those e.
facility components identified in USAR Table 5.1-8.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the QA Manual.
j.
Records of reviews performed for changes made to
)
procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the SRB and the CNRB.
1.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.
m.
Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analyses at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.
o.
Records of the service lives of all safety related hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.
p.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
DAVIS-BESSE, UNIT 1 6-19 Amendment No. 8,12,86,94,170,231 Order dated Oct. 24, 1980
ADMINISTRATIVE CONTROLS 1
6,11 Deleted l
6.12 HIGH RADIATION ARIB, l
As provided in paragragni 20.1601(c) of 10 CFR Part 20, the j
following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601'a) and (b) of 10 CFR Part 20:
a 6.12.1 High radiation areas with dose rates not exceeding 1.0 rem / hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation:
a.
Each entry way to such an area shall be barricaded and conspicuously posted as a high radiation area.
Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
b.
Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area (s) and other appropriate radiation protection equipment and measures.
c.
Individuals qualified in radiation protection procedures (e.g.,
health physics personnel) and personnel continuously escorted by such individuals may be exempted from the requirement for a RWP or equivalent while performing their assigned duties provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.
d.
Each individual (whether alone or in a group) entering such an area shall possess:
1.
A radiation monitoring device that continuously displays radiation dose rates in the area; or 2.
A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or 3.
A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel l
radiation exposure within the area, or 1
4.
A self-reading dosimeter (e.g.,
pocket ionization chamber or electronic dosimeter) and be under the surveillance, as specified in the RWP or equivalent, waile in the area, by means of closed circuit television, by personnel qualified in radiation protection procedures responsible for controlling i
personnel radiation exposure in the area.
DAVIS-BESSE, UNIT 1 6-20 Amendment No. 8,12231 1
j
6 ADMINISTRATIVE CONTROLS l
6.12.1 (continued) e.
Except for individuals qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.
6.12.2 Locked high radiation areas with dose rates greater than 1.0 rem / hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads / hour at 1 meter from the radiation source or from any surface penetrated by the radiation:
a.
Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked door, gate,in addition:or other barrier that prevents unauthorized entry,
- and, 1.
All keys to such doors, gates, or other barriers shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee.
2.
Doors, gates, or other barriers shall remain locked except during periods of personnel or equipment entry or exit, b.
Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area (s)d measures, ppropriate radiation protection and other a equipment an c.
Individuals qualified in radiation protection procedures may be exempted from the requirement for a RWP or i
equivalent while performing radiation surveys in such i
areas provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.
d.
Each individual (whether alone or in a group) entering such an area shall possess:
1.
A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or 2.
A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote recei4er monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or A self-reading dosimeterchamber or electronic dosimeter) pocket ionization (e.g.,
3.
- and, (i)
Be under the surveillance, as specified in the RWP or equivalent, while in the area, by an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or DAVIS-BESSE, UNIT 1 6-20a Amendment No. 231 l
L f
ADMINISTRATIVE CONTROLS l
6.12.2 (continued)
(ii)
Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, by personnel qualified in radiation protection procedures responsible for controlling personnel radiation exposure in the area and with the means to communicate with and control every indi.'.'idual in the area, or 4.
In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.
e.
Except for an individual qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.
f.
Such individual areas that are within a larger area that is controlled as a high radiation area, where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area, need not be controlled by a locked door or gate, but shall be barricaded and conspicuous, and a clearly visible flashing light shall be. activated at.the area as'a warning device.
t a
DAVIS-BESSE, UNIT 1 6-20b Amendment No. 231 l
f l
l 4
e f
ADMINISTRATIVE CONTROLS 6.14 FROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retained as rewired by Specification 6.10.2.p.
This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate anal evaluations justifying the change (yses or s), and 2)
A determination that the change will maintain the 3
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.
6.15 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as rew ired by Specification 6.10.2.p.
This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate anal evaluations justifying the change (yses or s), and 2)
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, l
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, j
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.
DAVIS-BESSE, UNIT 1 6-22 Amendment No. 86,170,184,231