ML20105C962
| ML20105C962 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/10/1992 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20105C963 | List: |
| References | |
| NUDOCS 9209240148 | |
| Download: ML20105C962 (9) | |
Text
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)(QLF CREEK NyCLEAR OPERATING CORPORATION WOLF CREELSEliEPAT?NG STATION QQU ET NO. 50-482 AMENDMENT TO FACILITY OPERATING.. LICENSE Amendment No. 56 License No. NPf-42 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated June 19, 1992, 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 I; B.
The faci' 's will operate in conformity with the application, as amended,. ; 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 conoucted without et L,ngering the health and safety of the public, and (ii) that such activities will be conducted in compliance witL the Comission's regulations; D.
The issuance-of this license 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 accordante with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9209240148 9209iO PDR ADOCK 05000482.
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Accordirq1y, the li.ense is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.0.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Sorcificatiqai The Technical Specifications contained in Appendix A, as revised through Amendment No. 56, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of lisuance.
FOR THE NUCLEAR REGULATORY 00KMISS10N MM Suzanne'(. Black, Director Project Directorate IV-2 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Techn. cal Specifications Date of issuance:
September 10. 1992
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 56.
ZILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to :naintain document.
completeness.
REMOVE INSERT 3/4 3-41 3/4 3-41 6-7 6-7 6-15 6-15 ver-e
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TABLE 3.3-6 fConLLnad.1 TABLE NOTATIONS
- With fuel in the respective fuel storage pool.
- With irradiated fuel in the fuel storagt areas or fuel building.
3
- 1 rip Setpoint concentration value (gCi/cm ) is to be established such that the actual cubmersion dose rate would not exceed 2 mk/h in the control rrom.
3
- irip Setpoint concentration value (sci /cm ) is to be established such that the actual submersion dose rate would not exceed 4 mR/h in the fuel building.
3
- Trip Setpoint concentration value (#Cl/cm ) is to be established such that the actual submersion dose r'te would not exceed 9 mR/h in the containment building. The Setpoint value may be increased up to the equivalent limits of Section 3.1 of the ODCM in accordance with the methodology and l
parameters in the ODCM during containment purge or vent provided the Setpoint value does not exceed twice the maximum concentration activity in the containment deteruined by the samylt analysis performed prior ta each release in accordence with Table 3-1 of the ODCM.
l ACTION STATEM[NIS ACTION 26 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge valves are I
maintained closed.
ACTION 27 - With the number of OPERABLE channels cne less than the Minimum Channels OPERABLE requirement, isolate the Control Room Emergency Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculation mode within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or with no OPERABLE channels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 28 - With less than the Minimum Channels OPERABLE requirement, operation may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Secpoint is provided in the fuel' area.
Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the tuel building.
ACTION 29 - Must satisfy the ACTION requirements for Specification 3.4.6.1.
ACTION 30 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, isolate the fuel Puilding Ventilation System and initiate operation of the-Emergency Exhaust System to maintain the fuel building at a negative pressure within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or with no OP?RABLE channels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
WOLF CREEK - UNIT 1 3/4 3-41 Amendment No. 79, 56 i
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TABit 4. 3-3 RADI AT!3H MONITORING INSTRUMENTA!!ON FOR PLANT g
OPERATIONS SURVilLLANCE REQUIREFENTS_
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ANALOG MODES FOR E
CHANNEL wilCH SURvit -
CHAMNEL CHANNEL OPERATIONAL 1ANCE 15 E
FUNCTIONAL UNIT CHECK CAtlBRATION TEST REQtil RED
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1.
Containment a.
Containment Atmosphere-Gaseous Radioactivity-l High (GT-RE-31 & 32) 5 R
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Gaseous Radioacti-ity-RCS Leakage Detection (G1-RE-11 & 32) 5 R
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3, 4 u,
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Particulate 2
Radioactivity -
RCS Leakage Detection E
(GT-RE-31 & 32)
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1, 2, 3, 4 u.
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2.
Fuel Building a.
Fuel Buildir.g Exhaust-Gaseous Radieactivity-High (GG-RE-27 & 28) 5 R
M b.
Criticality-High Radiation Level
- 1) Spent F"el Pool 5
R M
(50-RE- ' & 38)
- 2) New Fuel Pool I
(SC-RE-35 & 36) 5 R
M 3.
Control Room Air Intake-Gaseous Radioactivity-High (GK-RE-04 & 05) 5 R
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- With fuel in the respettive fuel storage pool.
- With irradiated fuel in the fuel storage areas or fuel building.
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ADMIN 1STRAT1VE CONTROL 5 6.3 UNIT staff OVALIFICAT1W (Continued) b.
The position of Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
The NSRC members shall meet or exceed the requirements of ANSI /ANS c.
3.1-1981.
6,4 TRAlHING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager Training and shall meet er exceed the requirements and recommendations of Section 5 of ANSl/ANS 3.1-1978 with the following exceptions:
The training program for Licensed Operators and Senior Operators a.
shall meet or exceed the requirements and recommendations of Section 5 of ANSl/ANS 3.1-1981 as endorsed by Regulatory Guide 1.8, Revision-2, and 10 CFR Part 55.
b.
Training shall include familiarization with relevant industry operational experience identified by the ISEG or another plant group.
6.5 REVIEW AND AUD11 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)
FUNCT?fd 6.5.1.1 The PSRC shall function to advi*e the Director Plant Operatioas on all matters related to nuclear safety.
COMPOSIT.liH 6.5.1.2 The PSRC shall be composed of the:
Member:
Manager System Engineering l
Member:
Manager Operations Member:
Manager Technical Support Member:
Manager Maintenance and Modifications Member:
Manager Instrumentation and. Control Member:
Supervisor Reactor Engineering.
- tiember:
Manager Radiation Protection Member:
Manager Chemistry Member:
Supervisor Results Engineering Chairman:
Manager Plant Support ALTERNATES-6.5.1.3 All alternate members shall be appointed in writing by the-PSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSRC r.ctivities at any one time.
WOLF CREEK UNIT 1 6-7 Amendment No. 20, 25, A$, 54, 56
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ADMINISTRATIVE CONTROLS HEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or his designated alternate.
OUORUM 6.5.1.5 The quorum of the PSkC necessary for the performance of the PSRC responsibility and authority provisions of these Techni.nl Specifications shall consist of the Chairman or his designated alterna.c and four members including alternates.
RESPONSIBILITIES
- 6. 5.1. 6 The PSRC shall be responsible for:
a.
Review of: (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specification 6.8 m changes thereto, and (3) any other proposed procedures or changes thsteto as determined by the Director Plant Operations to affect l
nuclear safety; b.
Review of all proposed changes, tests and experiments which may involve an unreviewed safety question u defined in Section 50.59, 10 CFR; c.
Review of all proposed changes to Technical Specifications or the Operating License; d.
Review of all safety evaluations performed under the provision of Section 50.59(a)(1),10 CFR, for changes, tests and experiments; e.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Vice President Operations, and to the Nuclear Safety Review Committee (NSRC);
f.
Review of all REPORTABLE EVENTS; g.
Review of reports of operating abnormalities, deviations from expected performance of p'lant equipment snd of unanticipated deficient. s in the design or operation of stri tures, systems or components that affect nuclear safety; h.
Perfonnance of special reviews, investigations or analyses and reports thereon as reauested by the Chairman, NSRC; i.
Review of the plant ser urity Plan and implementing procedures and
.shall submit recoK
-;d changes to the NSRC; j.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the NSRC; WLF CREEK UNIT 1 6-8 Amendment No. 4, 45
ADMINISTRATIVE CONTR0lS PROCEDURELAHD PROGRAMS (Continued) 6.8.3 Changes to Procedures a.
Temporary changes to Major Procedures, of t..e categories listed in Specification 6.8.1 which do not change the intent or generate an unreviewed safety question of the original or subsequent approved procedure, may be made provided such cnanges to operating procedures are approved by the Shift Supervisor (SR0 licensed) and one of the Call Su)erintendents.
For temporary changes to Major Procedures under t1e jurisdiction of groups other than Operations (e.g.,
Maintenance, Instrumentation and Control, Reactor Engineering, Chemistry, Health Physics) which do not change the intent or generate un unreviewed safety question, changes may tm made upon approval of the Cognizant Group Leader and a Call Superintendent.
All temporary changes to Major Procedures (made by a Call Superintendent and either a Cognizant Group Leader or the Shift Supervisor) shall subsequently be reviewed by the PSRC and approved by the Director Plant Operations within 14 days, except that temporary changes to Major Procedures made during a refueling outage may te reviewed and approved at any time prior to initial criticality of the reload core. All permanent changes to Major Procedures shall be made in accordance with Specification 6.8.2.a.
b.
All temporary or permanent changes to Minor Operating Procedures (checkoff lists, alarm resaonses, data sheets, operating instructions, etc.) shall 3e approved by the Shift Supervisor, and shall be subsequently reviewed and approved by the Operations PSRC Subcommittee.
All temporary or permanent ch.nges to other Minor Procedures under the jurisdiction of groups other than Operations (e.g., Maintenance, Instrumentation and Control, Reactor Engineering, Chemistry, Health Physics) shall be approved by a Cognizant Group Letder and shall be subsequently reviewed and approved by the appropriate PSP.C Subcommittee.
c.
Temporary changes to Corporate Emergency Plan implementing procWures may be made provided that:
(1) the intent of the original procedure is not altered, (2) the change is approved by the Manager Technical Services, and (3) the change is documented, reviewed by appropriate Corporate and plant personnel and approved by the President and Chief Executive Officer within 14 days of the implementation.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Reactor Coolant Sources Outside Containmep_t, 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 the approoriate portions of the Containment Spray-System, Safety injection System, Chemical and Volume Control l:ystem, RHR System, and the Nuclear Sampling System (PASS only).
The program shall include the following:
WOLF CREEK - UNIT 1 6-15 Amendment No. ( W, 56
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e ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 1)
Preventive maintenance and periodic visual inspection requirements, and 21 Integrated leak test requirements for each system at refueling c/cle intervals or less.
b.
In-Plant Radiation Monitorina A program which will ensure the capability to accurately deterwine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the following:
1)
Training of personnel, 2)
Procedures for monitoring, and 3)
Provisions for maintenance of sampling and analysis equipment.
c.
Secondary Water Chemistry t
A program for mon'toring of secondary water ch2mistry to inhibit steam ge.eretor tube degradation.
This program shall include:
1)
Identification of a sampling schedule for the critical variables and control points for these variables, 2)
Identification of the procedures used to measure the values of the critical variables, 3)
Identification of process saiapling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, 4)
Procedures for the recording and management of data, 5)
Procedures defining corrective action for all off-control point chemistry conditions, and 6)
A procedure identifying:
(a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Post-accident Sampling A program which will ensure the capaoility 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:
1)
Training of personnel, 2)
'*ocedures for sampling and analysis, and 3)
.tovisions for maintenance of sampling and analysis equipment.
WOLF CREEK UNIT 1 6-16
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