ML20248H628
| ML20248H628 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/03/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248H631 | List: |
| References | |
| NUDOCS 8910110300 | |
| Download: ML20248H628 (12) | |
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. UNITED STATES
,j NUCLEAR REGULATORY COMMISSION yh _
e E-WASHINGTON, D. C. 20655 TOLEDO EDIS0N COMPANY AND' THE: CLEVELAND ELECTRIC: ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1
' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.139 License No. NPF - 1. ;
The Nuclear Regulatory Commission (the Connission) has found that:
The application for amendment by the Toledo Edison Company)and(q
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A.
The Cleveland Electric Illuminating Company -(the licensees dated June 20,~1988 complies with the standards and requirements of the
- Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B.
-The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance.(1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph.2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
8910110300 891003 PDR ADOCK 05000346 P
PDC L. _ ___ _ _ - _ _ _ - _ _ _ - -.
-2 (a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.139, are hereby incorporated in the license.
The Toledo. Edison 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 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION wp d John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V, & Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of. Issuance: October 3, 1989
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ATTACHMENT TO LICENSE AMENDMENT NO. 139 L
FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 ReplacethefollowingaagesoftheAppendix"A"TechnicalSpecifkcationswith the attached pages. T1e revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 6-6 6-6 6-7 6-7 6-11 6-11 6-12 6-12 6-12a 6-12a 6-13 6-13
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ADMINISTRATIVE CONTROLS
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5 6.3 FACILITY STAFF QUALIFICATIONS-6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 forcomparablepositions,exceptfor(1)-
the Radiological Controls Superintendent who shall meet or exceed the l
qualifications of Regulatory Guide 1.8, September 1975 and-(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.
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 Training Director and shall meet or. exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and of 10 CFR 55.59.
6.4.2.~ A training program for the Fire Brigade shall be maintained under the' direction of the Nuclear Training Director.
6.5' REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)
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. 9,37,59,9E,Jgg,N45, 138
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ADMINISTRATIVE CONTROLS' COMPOSITION:
j 6.5.1.2 The Station Review Board shall be_ composed of the:
Chairman:
- Station Review Board Chairman
- Member:
Assistant Plant Manager, Operations L
Member:
Assistant Plant Manager, Maintenance Member:
Technical Support Manager Member:
Radiological Controls Superintendent l-Member:
Operations Engineering Supervisor (Plant)
Member:
An Engineering Director
' Member:
Quality Assurance Supervisor j
Member:
Operations Superintendent (Plant)
I
- Designated in writing by the Plant Manager. The Chairman will be drawn from SRB members.
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SRB Chairman; however, no more than two alternates shall participate as voting members in SRB activities at any one time.
MEETING FREQUENCY 6.5.1.4 The SRB shall meet at -least once per calendar month.and as 4
convened by the SRB Chairman or his designated alternate.
QUORUM
- 6. 5.1. 5 A quorum of the SRB shall consist of the Chairman or his designated i
alternate and four members including alternates.
RESPONSIBILITIES-i
- 6. 5.1. 6 The Station Review Board shall be responsible for:
a.
Review of plant administrative procedures and changes thereto.
b.
Review of the safety evaluation for 1) procedures, 2) changes to procedures, equipment or systems, and 3) tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions do not constitute an unreviewed safety question.
c.
Review of proposed procedures and changes to procedures and equipment determined to involve an unreviewed safety question as defined in 10 CFR 50.59.
DAVIS-BESSE, UNIT 1 6-6 Amendment No. JZ,76,98,109,J38,139 l
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,is 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 co' des, regulations, orders, Technical Specifications, or Operating Licenseerequirements having nuclear safety significance or reports of abnonnal degradation of
-systems designed to contain radioactive material, f.
Review of all proposed changes to the Technical Specifications or the Operating License.
9 Deleted h.
Review of reports of significant operating abnormalities or devi-ations-from normal and expected performance of plant equipment that affect plant safety.
1.
Review of the Industrial Security Plan, the Security Training and Qualification Plan, and the Security Contingency Plan, and changes-thereto.
j.
Review of the Davis-Besse Emergency Plan and changes thereto.
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 requested by the Company Nuclear Review Board.
m.
Review of all REPORTABLE EVENTS.
n.
Review of all Safety 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.
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Review of the changes to the PROCESS CONTROL PROGRAM.
l r.
Review of the Annual Radiological Environmental Operating Report.
s.
Review of the Semiannual Radioactive Effluent Release Report.
- DAVIS-BESSE, UNIT 1 6-7 Amendment No. 27,2j5,93,9E,JD9, 139 1
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ADMINISTRATIVE CONTROLS f.
I' AUTHORITY
.6.5.1.7 The Station Review Board shall:
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.a.
. Recommend to the Plant Manager written approval or disapproval of items considered under Sections 6.5.1.6 a, c, d, f, i and j.
l b.
Render determinations in writing with regard to whether or not i
each item considered under Sections 6.5.1.6 a, c, d and f above constitutes an unreviewed safety question as defined in 10 CFR 50.59.
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 Vice l
President,' Nuclear and the Company Nuclear Review Board of
' disagreement between the SRB and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
d.
Make recommendations in writing to the Plant Manager that actions reviewed under Section 6.5.1.6 b above do not constitute an unreviewed safety question.
RECORDS 6.5.1.8 The Station Review Board shall maintain written minutes of each meeting and copfes shall be provided to the Plant Manager, Vies President,
'l Nuc1 car'and Chairman of the Company Nuclear Review Board.
6.5.2 COMPANY FUCLEAR REVIEW BOARD (CNRB)
FUNCTION 6.5.2.1 The. Company Nuclear Review Board (CNRB) shall function to provide independent review and audit of designated activities in the areas
.of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, d.
Metallurgy, e.
Instrumentation and control, f.
Radiological safety, g.
Mechanical and electrical engineering, and h.
Quality assurance practices.
DAVIS-BESSE,-UNIT 1 6-8 Amendment No. 27,56,98, 109
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ADMINISTRATIVE CONTROLS AUDITS i
6.5.2.8 Audits of facility activities shall be performed under the cognizance of the CNRB.
These audits shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire station staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d.
The perfonnance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
e.
The Davis-Besse Emergency Plan and implementing procedures at lear.t l
once per 12 months.
f.
The Industrial Security Plan and implementing procedures at least l
once per 12 months, t
9 Any other area of facility operation considered appropriate by the CNRB.
h.
The Facility Fire Protection Program and implementing procedures at i
least once per 24 months.
i.
An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protec-tion firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at I
least once per 36 months.
1 k.
The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months.
1.
The 0FFSITE DOSE CALCULATION MANUAL and implementation of procedures at least once per 24 months.
m.
The PROCESS CONTROL PROGRAM and implementation of procedures for proces-sing and packaging of radioactive wastes at least once per 24 months.
DAVIS-BESSE, UNIT 1 6-11 Amendment No. J2,27,7/,EE,139
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ADMINISTRATIVE CGNTROLS AUTHORITY' 6.5.2.9 ; The. Company Nuclear Review Board shall report to and advise the.Vice President, Nuclear, on those areas of responsibility specified in Sections 6~5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of Company Nuclear Review Board activities shall be prepared, approved and distributed as indicated below:
.a.. Minutes-of each CNRB meeting shall be prepared, approved and forwarded to the Vice President, Nuclear and CNRB members within 14 days' follow-ing each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared,. app, roved and forwarded to the Vice President, Nuclear.
and CNRB members within 14. days following completion.of the review.
-c._-Audit. reports encompassed by Section 6.5.2.8 above, shall be forwarded
.to the Vice President, Nuclear and CNRB members and.to the management positions responsible for the areas audited within 30 days after completion of-the audit.
6,5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:
a.
Plant procedures required by Section 6.8.1 and changes thereto shall be prepared, reviewed'and approved.
Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group 1
which prepared the procedure or procedure change.
Plant procedures other than plant administrative procedures will be approved as delineated in writing by individuals holding positions not lower-than one management level below the Plant Manager.
The Plant Manager will approve plant administrative procedures, Industrial Security Plan Implementing Procedures and Davis-Besse Emergency Plan Implementing Procedures.
b.
Temporary approval of changes to plant procedures cited in Section 6.8.1 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 plant procedures, which may involve a change in intent of the approved 1
' DAVIS-BESSE, UNIT 1 6-12 Amendment No. 72,27,86,93,98,109, 139 l
ADMINISTRATIVE-CONTROLS procedures, the person authorized in Section 6.5.3.la to approve the I
procedure shall approve the change.
c.
Proposed changes or modifications to plant structures, systems and components shall be reviewed as designated by the Plant Manager.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications.
Implementation of modifications to plant structures, systems and components shall be approved by the Plant Manager.
d.
Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Safety Analysis Report shall be reviewed by an individual / group other than the individual / group which prepared the proposed test or experiment and shall be approved by the Plant l
Manager.
e.
Individuals responsible for reviews performed in accordance with Section 6.5.3.1 a, b, c and d above shall meet or exceed the appropriate qualification requirements of Section 4.2, 4.3.1, 4.4 or 4.6 of ANSI 18.1, 1971, and be previously designated by the Plant Manager.
Each such review shall include a determination of whether an additional, cross disciplinary, review is necessary.
If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.
f.
Each review will include a determination of whether an unreviewed safety question is involved as defined in 10 CFR 50.59.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of SECTION 50.73 to 10 CFR PART 50, and b.
Each REPORTABLE EVENT shall be reviewed by the SRB, and the results of this review shell be submitted to the CNRB and the Vice Presioent, Nuclear.
DAVIS-BESSE, UNIT 1 6-12a Amendment No. J09,139 (Next page is 6-13)
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ADMINISTRATIVE CONTROLS-1 E
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- 6. 7 ' SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is H,
violated:
L a.
The facility shall be placed in at least HOT STANDBY. within'one hour.
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 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 I
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 of the violation.
i
- 6. 8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures reconnended in Appendix "A" of Regulatory Guide 1.33, November,1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Industrial Security Plan implementation.
j e.
Davis-Besse Emergency Plan implementation.
l f.
Fire Protection Program implementation.
g.
The radiological environmental monitoring program.
h.
1.
Offsite Dose Calculation Manual implementation.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth in 6.5.3 above.
4 DAVIS-BESSE, UNIT 1 6-13 Amendment No. 9 JZ,27,86,9E.709, 139
~ ADMINISTRATIVE CONTROLS 6.8.3
. deleted)
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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:
j (1) Preventive maintenance and/or periodic visual inspection requirements, and (ii)' Integrated leak test requirements for each system at 4
refueling cycle intervals or less.
b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately deter-mine the airborne iodine concentration in vital areas under j
accident conditions. This program shall include the following:
(i)
Training of personnel, f
-(ii)
Procedures for monitoring, and (111)
Provisions for maintenance of sampling and analysis equipment.
I 1.
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I DAVIS-BESSE, UNIT 1 6-14 Amendment No. 9,72,fif,g, 109 I'