ML20150C451
| ML20150C451 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/09/1988 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150C453 | List: |
| References | |
| TAC-61468, NUDOCS 8803180257 | |
| Download: ML20150C451 (15) | |
Text
__________ - _
f UNITED STATES y
3s, g
NUCLEAR REGULATORY COMMISSION 5
l W ASHINGTON, D. C. 20555
/
....+
TOLEDO EDISON 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.109 License No. NPF-3 1.
The huclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Lompany (the licensees) dated January 22, 1986, as clarified August 25, 1987, December 28, 1987 January 15, 1988 and February 17, 1988 complies with the standards and requirements 4
of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safetyofthepublic,and(11)thatsuchactivitieswillbeconducted 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.
8803100257 000309 DR ADOCK 050 6
4
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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment ho.109, 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 May 9,1988.
FOR THE NUCLEAR REGULATORY COMMISSION 4W m
Kenneth E. Perkins, Director Project Directorate III-3 Division of Reector Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9,1988 v
. _ _. _ - = _ - - -
~
1 l
ATTACHMENT TO LICENSE AMEN 0 MENT NO.109 I
FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf page(s) are also provided to maintain document completeness, i
Remove Insert 3/4 6-18 3/4 6-18 6-6 6-3 6-7 6-7 6-8 6-8 6-12 6-12 6-12a i
6-13 6-13 6-14 6-14 4
J
.i E
i R
i 1
i 1
1 t
- - -. - - I
l I
TABLE 3.6-2 CONTAINMEh7 ISOLATION YALYES (Continued)
PENETRATION YALVE ISOLATION NUM3 ER NUMSER FUNCTION TTMi
~
(seconcs) 16 RC1719A Containment Yessel' Vent Header 10 16 RC17195 Containment Vessel Vent Header 10 18 f 55598 Steam Generator Secondary Watar Sasple Line 10 19 MU33 Normal RCS Makeup Line 10 19 i HP2A High Pressurs Injection Line 15 20 i NP2B High Prsssure lidection Line 15 21 DW6831A Domineralized Water Supply Line 10 21 DW68318 Demineralized Water Supply Line 10 22 i HF2D High Pressure Injection Line 15 25 C31531 Containment Spray Line 25 25 C31530 Containment Spray Line 25 30 i. DRSA Containment Su=p Emergency Recir 71 Line 31 i DK98 Containment Su=p Emergency Recirt Line 71 32 MC1773A RC5 Drain to RC Drain Tank 10 32 RC17733 RCS Drain to RC Drain Tank 10 37 i FW601 Main Feedwater Line 15 38 f FW612 Main Feedwater Line 15
" 39 i M5100 Main Staam Line 5
l
~39 i IC511A Main Steam Line 10 39 i MS375 Main Staam Line 10 39 i M5100-1 Main $taam Line 10
" 40 l MS101 Main Staam Line 5
l
~40 f IC5118 Main Staam Line 10 l
40 f MS394 Main Staan Line 10 l
40 i MS101-1 Mrin Stana Line 10 1
I DAVIS-BESSE, UNIT 1 3/4 6-17 Amenament No. /, 72 1
4 o
I
TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)
PENETRATION VALVE ISOLATION NUMBER NUMBER FUNCTION TIME (seconds) 41 RC232 Pressurizer Quench Tank Circulating Inlet Line 10 42A SA2010 Service Air Supply Line 10 42B CV5010E Containment Vessel Air Sample Return 15 43A IA2011 Instrument Air Supply Line 10 43B CV5011E Containment Vessel Air Sample Return 15 44A CF1541 Core Flood Tank Fill and N2 Supply Line 10 44B NN236 Pressurizer Quench Tank N2 Supply Line 10 47A CV1545 Core Flood Tank Sample Line 10 47B CV1542 Core Flood Tank Vent Line 10 48 RC229A Pressurizer Quench Tank CirculatinF Ou'3et Line 10 t
48 RC229B Pressurizer Quench Tank Circulating Outlet Line 10 50 #
HP2C High Pressure Injection Line 15 51 CV5037 Hydrogen Purge System Exhaust Line 60 51 CV5038 Hydrogen Purge System Exhaust Line 60 52 MU66A Reactor Coolant Pump Seal Supply 12 53 MU66B Reactor Coolant Pump Seal Supply 12 54 MU66C Reactor Coolant Pump Seal Supply 12 55 MU66D Reactor Coolant Pump Seal Supply 12 56 MU38 Reactor Coolant Pump Seal Return 12 56 MU59A Reactor Coolant Pump Seal Return 30 56 MU598 Reactor Coolant Pump Seal Return 30 56 MU59C Reactor Coolant Pump Seal Return 30 56 MU59D Reactor Coolant Pump Seal Return 30 57 #
MS603 Steam Generator Blowdown Line 80 60 f MS611 Steam Generator Blowdown Line 80
?
DAVIS-BESSE, UNIT 1 3/4 6-18 Amendment No. 19. 109
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the miniaun qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Chemistry and Health Physics General Superintendent l
vho shall meet or exceed the 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 l
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 Fire Marshall and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.
6.5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)
FUNCTION 6.5.1.1 The Station Review Board (SR3) shall function to advise the
. Plant Manager on all matters related to nuclear safety.
l l
i s
1 f"[
1
'1 i
DAVIS-BESSE UNIT 1 6-5 Amendment No.f.. 9),96
I 1 ADMINISTRATIVE CONTROLS y COMPOSITION 1 6.5.1.2 The Station Review Board shall be composed of the: Chairman: Station Review Board Chairman
- Member:
Assistant Plant Manager, Operations Member: Assistant Plant Manager, Maintenance Member: Technical Support Manager Member Chemistry and Health Physics General Superintendent i Member: Operations Engineering Supervisor (Plant) Member: An Engineering Director or Performance Engineering Manager l Member: Operations Ouality Assurance Manager Member: Operations Superintendent (Plant)
- Designated in writing by the Plant Manager. The Chairman vill be drawn from SRB members.
l 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 l eembers in SRB activities at any one tine. MEETING TRE01'ENCY l 6.5.1.4 The SRB shall meet at least once per calendar nonth'and as convened by the SRB Chatruan or his designated alternate. Ol'ORly l 6.5.1.5 A quorum of the SRB shall consist of the Chairman or his desig-nated alternate and four members including alternates. j RESPONSIBILITIES i 6.5.1.6 The Station Review Board shall be responsible for: i a. Review of plant administrative procedures and changes thereto. l b. Review of the safety evaluation for 1) procedures, 2) changes to procedures, equiptent or systems and 3) tests or experiments l completed under the provisions of 10 CFR 50.59, to verify that 1 such actions do r,ct constitute an unreviewed safety question. 1 j c. Review of proposed procedures and changes to procedures and l equipment determired to involve an unreviewed safety question as defined in 10 CFR 50.59. i l '. D i j ] DAVIS-BESSE, l' KIT 1 6-6 Amendment No. !!,76,98,109 ) l
4=Aa. a F 4 E ADMINISTRATIVE CONTROLS e d. Review of proposed tests or experiments determined to involve an unreviewed safety question as defined in 10 CFR 50.39. e. Investigation of all violations of the Technical Specifications including preparation and forwarding of reports covering eval-uation and recommendations to prevent recurrence to the Vice l President, Nuclear and to the Chairman of the Company Nuclear Review Board. l f. Review of all proposed changes to the Technical Specifications er the Operating License. I g. Review of reports of violations of codes, regulations, orders or i Operating License requirements having nueJear safety significance. i ) h. Review of reports of significant operating abnormalities or devi-atione frem normal and expected performance of plant equipment that i I affect plant safety. l i. Review of the Plant Security Plan and changes thereto, j j. Review of the Emergency Plan and changes thereto. k. Review of items which may constitute potential nuclear safety hazards as identified during review of facility operations. 4 1 ] 1. Investigations or analyses of special subjects as requested by the Company Nuclear Review Board. 4 m. Review of all REPORTA3LE EVENTS. I n. Review of all Safety Limit Violation Reports (Section 6.7). o. Review of any unplanned, accidental or uncontrolled radioactive i releases, evaluation of the event, ensurance that remedial action is identified to prevent recurrence, review of a report j covering the evaluation and forwarding of the report to the j Plant Manager and to the CNRB. p. Review of the OFFSITE DOSE CALCL'LATION MANUAL and implemen-4 l tation of procedures at least once per 24 months. i I i l q. Review of the PROCESS CONTROL PROGRAM and implementation of i procedures for processing and packaging of radioactive wastes i at least once per 24 months. i r. Review of the Annual Padiological Environmental Operating j Report. j i 1 I s. Review of the Semiannual Radioactive Effluent Release Report. ( ! I f DAVIS-BESSE, UNIT 1 6-7 Amendrent No. 27,86.93.pf, 109 i
.t ADMINISTRATIVE CONTROLS f AUTHORITY 6.5.1.7 The Station Review Boerd shallt a. Recocaend to the Plant Manager written approval or disapproval i of items considered under Sections 6.5.1.6 a, c. d, f. i and j. { b. Render determinations in writirg with regard to whether or not 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 hours to the Vice l i President. Nuclear and the Company Nuclear Review Board of disagreceent between the SRB and the Plant Managert however, the Plant Manager shall have responsibility for resolution of such I disagreements pursuant to 6.1.1 above. i d. Make recommerdations in writing to the Plant Manager that actions reviewed under Section 6.5.1.6 b above do not i constitute an unreviewed safety question. [ RECORDS 6.5.1.8 The Station Review Board shall maintain written minutes of each meeting and copies shall be provided to the Plant Manager. Vice President. l Nuclear and Chairman of the Coepany Nuclear Review Board, i 6.5.2 COMPANY NUCLEAR RFVIEW BOARD (CNRR) i FUNCTION 6.5.2.1 The Ccepany Nuclear Review Board (CNRB) shall function to provide independent review and audit of designated activities in the areas of: i a. Nuclear power plant operations. f b. Nuclear engineering. I c. Chemistry and radiochemistry, d. Metallurgy. l 3 e. Instrumentation and control. 1 f. Padiological safety, g. Mechanical and electrical engineering, and 7 h. Quality assurance practices. I i j DAVIS-BESSE. UNIT 1 6-8 Amendment No. 27.36,93. 109 4
ADMINISTRATIVE CONTROLS ALTITS 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 Teebnical 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 performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months. The Station E.nergency Plan and implementing procedures at least e. once per 12 months. f. The Station Security Plan and implementing procedures at least once per 12 months. g. Any other area of facility operation considered sppropriate by the CNRB. h. The Facility Fire Protection Program and implementing procedures at 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 i utilizing either qualified offsite licensee personnel or an outside fire protection fire. j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months. k. The performance of activities required by the Quality Assurance Program to meet the provisions of Pasvletory Guide 1.21 Revision 1, June 1974 and Regulatory Cvide 4.1, Revision 1 April 1975 at least once per 12 months. ) DAVIS-BESSE, UNIT 1 6-11 Amendment No. JJ, J/, 7), 86
'f a ADMINISTRATIVE CONTROLS l 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 l l Sections 6.5.2.7 and 6.5.2.8. I RECORDS 6.5.2.10 Records of Company Nuclear Review Board activities shall be prepared, approved and distributed as indicated below: [ i a. Minutes of each CNRB meeting shall be prepared, approved and j forwarded to the Vice President. Nuclear and CNRB members within l i I 14 days following each meeting. i b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President, j 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 eembers and to l the management positions responsible for the areas audited within 30 days after completion of the audit. l l 6.5.3 TECHNICAL REVIEk' AND CONTROL ACTIVITIES l i 6.5.3.1 Activities which affect nuclear safety shall be conducted as foilovsa 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 l other than the individual / group which prepared the procedure or j procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change. Plant procedures other than plant administrative proce-dures vill be approved as delineated in writing by individuals l holding positions not lower than one management levet below the Plant Manager, n e Plant Manager will approve plant adminis-trative procedures. Security Implementing Plant Procedures and Emergency Implementing Plant Procedures. b. Teeporary approval of changes to plant procedures cited in l Section 6.8.1 which clearly do not change the intent of the l approved procedures, can be made by two members of the plant management staff, at least one of whom holds a Senior Reactor 2 l Operator's License. For changes to plant procedures which may '1 DAVIS-BESSE. UNIT 1 6-12 AMENDMENT NO. h7.77.5(.77.77.109 ) 1
ADMINISTRATIVE CONTROLS involve a change in intent of the approved procedures, the person authorized in $sceton 6.5.3.la to approve the procedure shall approve the change. c. Proposed changes or mcdifications to plant structures, systees 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 /aroup which designed the modification, but who may be from the same organization as the individual / group which designed the modifications. Implementation of rodifications to plant structures, systems and 3 components shall be approved by the Plant Manager. l 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 l and approved by the Plant Manager, e. Individua1r *esponsible for reviews performed in accordance 1 with Section 6.5.3.1 a, b, e and d above shall swet or exceed l the appropriate qualification requirements of Section 4.0 ] 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 j a determination of whether an additional, cross disciplinary, i 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 s ] unreviewed safety question is involved as defined in 10 CFR 50.59. 6.6 REPCRTABLE EVENT ACTION I f 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: J 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 shall be submitted to the CNRB and the Vice President, Nuclear. 1 ] l l 1 i j DAVIS-BESSE, UNIT 1 6-12a AMENDMENT NO.109 (Sext page is 6-13) 1
. ~. -.. = k i ADMINISTRATIVE CONTROLS f 6.7 SAFETY LIMIT VIOLATION i 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: l a. The facility shall be placed in at least HOT STANDBY vithin one hour. b. The Safety Limit violation shall be reported to the NRC j Operations Center by telephone as soon as possible and in all j cases within one hour. In addition the Vice President, j Nuclear and the CNRB shall be notified within 24 hours. g 1 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. P .{ ] d. The Safety Limit Violation Report shall be submitted to the Commission, the CNRB and the Vice President. Nuclear within l 14 days of the violation. } 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established implemented and main- ] tained covering the activities referenced below The applicable procedures recommended in Appendix "A" of a. j Regulatory Guide 1.33. November, 1972. j b. Refueling operations. i l Surveillance and test activities of safety related equipment. c. I d. Security Plan implementation. i e. Emergency Plan implementation. f. Fire Protection Program implementation. g. The radiological environmental monitoring program, i h. The Process Control Program. i. Offsite Dose Calculation Manual implementation. l 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. I i ) 1 J 9.!!.21.86.77. 109 ) DAVIS-BESSE. UNIT 1 6-13 Amendment No. i
ADMINISTRATIVE CONTROLS 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 lov as practical levels. The systems include makeup, letdown, seal injection, seal return, low pressure injection, containment spray, high pressure injection, vaste gas, primary sampling and reactor coolant drain systems. The program shall include the following: (1) Preventive maintenance and/or periodic visual inspection requirements, and (ii) Integrated leak test requireeents for each system at refueling cycle intervals or less. b. In-Plant Radiation Monitoring A program which vill ensure the capability to accurately deter-eine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following: (1) 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,!!,g(,)S, 109}}