ML19309F000
| ML19309F000 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/03/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19309F002 | List: |
| References | |
| NUDOCS 8004280299 | |
| Download: ML19309F000 (31) | |
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UNITED STATES y
3.- r NUCLEAR REGULATORY COMMISSION 3,, w { }' iC WASHINGTON, D. C. 20555
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V WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 26, 1979, 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 f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonabl.: assurance (i) that the activities authorized by this amendment :an be conducted without endangering the health and safety of the aublic, and (ii) that such activities will be conducted in (,ompliance with the Commission's regulations; i
D.
The issuance of thi. amendment will not be inimical to the common defense and security 'r 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 Commiss' ion's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amcoded by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. OPR-24 is herehy amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, are herehy incorporated in the license.
The licensee shall operate the facility in accordance with the Technical 4
Specifications.
3.
This 'ticense amendment is effective as of the date of its issuance.
i FOR THE NUCLEAR REGULATORY C0fitiISS10N 1
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A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
1 Changes to the Technical Specifications Date of Issuance: APR 0 31980 1
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/cp '" " 0%,Io, UNITED STATES fi
['i NUCLEAR REGULATORY COMMISSION N. 'j %. E WASHINGTON, D. C. 20555 g
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATING LICENSE a
Amendment Nn.48 License ko. OPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Conpany (the licensee) dated. September 26, 1979, 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 f acility 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 anendment 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.
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2 Accordingly, the license is amended by changes to the Technical 2.
Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. OPR-27 is hereby amended to read as follows:
1 (B) Technical Specifications t
i The Technical Specifications contained in Appendices
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A and B, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the f acility in accordance with the Technical j
f Specifications.
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Thi; license m.iandment is effective as of the date of its issuance.
FOR THE NUCLEAR. REGULATORY COMMISSION s'
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A. Schwent.er, Chief
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Operating Reactors Branch #1 Division of Operating Reactors J
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Attachment:
Changes to the Technical Specifications l
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i-Date of Issuance: APR 0 31980 i
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I ATTACHMENT TO LICENSE AMENDMENTS
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AMENDMENT NO. 43 TO FACILITY OPERATING LICENSE NO.
DPR-24 AMENDMENT NO. 48 TO FACILITY OPERATING LICENSE NO.
DPR-27 4
i DOCKET NOS. 50-266 AND 50-301 r
Revise Appendix A as follows.
Remove the following pages and insert identically numbered revised pages.
Table 15.3.13-1 l
Table 15.3.13-1 (continued)
Table 15.4.1-1 (first page) 15.5.1-1 j
15.6.i/2-1 Figure 15.6.2-1 l
Figure 15.6.2-2 Figure 15.6.2-3 Figure 15.6.2-4 15.6.3-1
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15.6.4/5-1 15.6.5-2 13.6.5-3 15.6.5-4 15.6.5-5 I
15.6.5-6 t
15.6.5-7 15.6.5-8 i
15.6.6-1 15.6.7-1 i
l 15.6.8-1 15.6.8-2 15.6'.8-3 15.6.9-1 4
15.6.9-6
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TABLE 15.3.13-1
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SAFETY RELATED SHOCK SUPPRESSCRS (SNUBBERS)
Snubber in Snubber Snubber 3nubber High Radiation Especially Inaccessible Accessible Incntion Area During Difficult to During Normal During Normal ID Number Incation Elevation Shutdown
- Remove Operation Operation Unit 1 1-HS-1 "A" Main Steam Line - West 100 X
l-HS-2 "A" Main Steam Line - East 100 X
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1-HS-5 "A" SG Side - North 66 X (2) 1-HS-6 "A" SG Side - Middle 66 X (2) 1-HS-7 "A" SG Side - South 66 X (2) 1-HS-3 "B" Main Steam Line - West 100 X
l-HS-4 "B" Main Steam Line - East 100 X
l-HS-8 "B" SG Side - North 66 X (2) 1-HS-9,
"B" SG Side - Middle 66 X (2) 1-HS-10 "B" SG Side - South 66 X (2) 1-HS-ll "A" Main Feed Line at 66' 61 X
l-HS Containment Spray Header Above 66' 120 X
l-HS-16 Containment Spray Header Above 66' 120 X
l-HS-17 Pressurizer Relief Line 80 X
l-HS-18 Pressurizer Relief Line 80 X
l-HS-14 Power Operated Header-Pressurizer 78 X
Cubicle 1-HS-M74 Relief Valve Header-Pressurizer 80 X
Cubicle 1-HS-12 SIS Line - Regen. HX Cubicle 34 X
X (2) 1-HS-13 SIS Line at 21' Elevation 40 X
l-HS-19 Reactor Vessel Keyway 3
X (1)
X l-HS-20 Reactor Vessel Keyway 3
X (1)
X Unit 2 2-HS-36 "A" SG Side - North 66 X (2) 2-HS-37 "A" SG Side - Middle 66 X (2) 2-HS-38 "A" "G Side - South 66 X (2) 2-HS-32 "A" h.in Steam Line - East 100 X
2-HS-33 "A" Main Steam Iine - West 100 X
2-HS-39 "B" SG Side - North 66 X (2) 2-HS-40 "B" SG Side - Middle 66 X (2) 2-HS-41 "B" SG Side - South 66 X (2) l Amendment No. 43, Unit 1 AmkYWfLRA PRLJuaAfLJ
TABLE 15.3.13-1 (Continued)
Snubber in Snubber Snubber Snubber High Radiation Especially Inaccessible Accessible Snubber Area During Difficult to During Normal During Normal ID Number Location Elevation Shutdown
- Remove Operation Operation f
X 2-HS-34 "B" Main Steam Line - East 100 X
2-HS-35 "B" Main Steam Line - West 100 2-HS-21 Aux. Feed Line to "A"
SG 72 i
X 1
X 2-HS-23 SIS Line at 46' 50 X
2-HS-26 SIS Line at 46' 34 X
2-HS-24 At Overhead to Keyway at 26' 36 X
2-HS-29 Downstream of Valve PCV 434 80 X
2-HS-30 Downstream of Valve PCV 435 80 X
2-HS-M75 Downstream of Pressurizer Safety 80 Valve X
2-HS-28 Line to Power Operated Relief 77 Valves 2-HS-22 Beneath Valve 541 in "A" Loop 41 X
X Cubicle 2-HS-31 Reactor Vessel Keyway 3
X (1)
X 2-HS-27 Reactor vessel Keyway 3
X (1)
X 2-HS-25 Regen. HX Cubicle at 26' 34 X
X (2)
(1) High radiation during shutdown uith flux thi mble withdrawn.
(2) Accessible during normal operat: on for visue.1 inspection on ly.
- Modifications to this Table due to changes in high radiation areas shall be submitted to the NRC as part o: the next lj eense amendment Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
TABLE 15.4.1-1 hINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Check Calibrate Test Remarks 1.
Nuclear Power Range S (1) **
D (1)**
B/W (2)**
- 1) Heat balance M*(3)**
Q*(3)**
- 2) Signal to AT: bistable action (permissive, rod stop, trips)
- 3) Upper and lower chambers for axial off-set 2.
Nuclear Intermediate Range S (l) *
- N.A.
P (2)
- 1) Once/ shift when in service
- 2) Log level; bistable action (permissive, rod stop, trips) 3.
Nuclear Source Range S (1)
N.A.
P (2)
- 1) Once/ shift when in service
- 2) Bistable action (alarm, trips) 4.
Reactor Coolant Temperature S
R B/W (1)**
- 1) Overtemperature-Delta T (2)
- 2) Overpower - Delta T 5.
Reactor Coolant Flow S**
R M**
6.
Pressurizer Water Level S**
R M**
7 Pressurizer Pressure S**
R M**
8.
4 Kv Voltage & Frequency N.A.
R M**
Reactor protection circuits only 9.
Analog Rod Position S (1)**
R M**
- 1) With step counters
- By means of the movable in-core detector system.
- Not required during. periods of refueling shutdown, but must be performed prior to starting up if it has not been performed during the previous surveillance period.
Tests of permissive and low power trip bistable setpoints which cannot be done during power operations shall be conducted prior to startup if not done in the previous two weeks.
Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
15.5 DESIGN FEATURES 15.5.1 SITE Applicability Applies to the location and extent of the reactor site.
Objective To define those aspects of the site which affect the overall safety of the installation.
Specification I
The Point Beach Nuclear Power Plant is l>cated on property owned by Wisconsin Electric Power Company at a site on the shore of Lake Michigan, approximately 30 miles southeast of the city of Green Bay.
The minimum distance from the reactor containment center line to the site exclusion boundary as defined in 10 CFR 100.3 is 1200 meters.
l 15.5.1-1
. Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
15.6 ADMINISTRATIVE CONTROLS 15.6.1 RESPONSIBILITY 15.6.1.1 The Manager - Nuclear Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during absences from the Point Beach Nuclear Plant area of greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and where ready contact by telephone or other means is not assured.
15.6.2 ORGANIZATION OFFSITE 15.6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 15.6.2-1.
FACILITY S'ilFF 15.6.2.2 The Facility organization shall be as shown on Figure 15.6.2-2 and:
a.
Each on-duty shift shall normally be composed of at least the minimum shift crew composition as noted in Figure 15.6.2-2.
b.
At least one licensed Operator shall be in the control room when fuel is in either reactor, c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in either reactor.
e.
ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
15.6.1/2-1 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
BOARD OF DIRECTORS PRESIDENT WISCONSIN ELECTRIC POWER COMPANY OTHER EXECUTIVE VICE PRESIDENT OFF-SITE DEPARTMENTS WISCONSIN ELECTRIC POWER COMPANY REVIEW COMMITTEE DIRECTOR NUCLEAR POWER DEPARTMENT SUPERINTENDENT SUPERINTENDENT MANAGER NUCLEAR PROJECTS OFFICE NUCLEAR OPERATIONS A UR CE MANAGER'S SUPERVISORY STAFF MANAGEMENT ORGANIZATION CHART FIGURE 15.6.2-1 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
Manager -
(1)
Nuclear Operations Manager's Supervisory Assistant to (1)
Staff Committee the Manager l
OPERATIONS TRAINING MAINTEhANCE &
TECHNICAL SERVICES CONSTFUCTION Superintendent - (1)
Training (1)
Superintendent (1)
Superintendent (1)
Technical Services Maintenance &
Operations (FRO)
Supervisor Construction INSTFUMEtu l
& CONTROL REACTOR ENGINEERING 8
l Technical (1)
Instrument &
Reactor Radiochemical Assistant Control Eng. (1)
Engineer (1)
Engineer (1) l Shif t Supervisor (SRO)
Maintenance Health (1)
Technical Physicist Ona per shift Supervisors Technicians Assistants Technical Opercting Supervisor J.ssistants Onn per shift (SRO or RO The Operations Group shift makeup is the minimum size for operation in all 1.
Control Operator (RO) modes except cold shutdown of Point Beach Unit Nos. 1 and 2.
The Oper-One per shift-one unit ations Group shift makeup may be less than the minimum requirements for a Two per shift-two units period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to acconnodate unexpected absence of on-duty shift crew members, provided immediate action is taken to restore the shift makeup to within the minimum requirements.
In administrative matters and routine HP concerns, the HP reports directly Auxiiiary Operator 2.
to the Radiochemical Engineer; in matters of radiological health and safety Two per shift-one unit policy determination, interpretation, or implementation, the HP (based Thrso per shift-two units on HP judgment) reports directly to the Manager-Nuclear Operations.
3.
SRO - NRC Senior Reactor Operator License RO - NRC Reactor Operator License Amendment No. 43, Unit I CONDUCT OF PIANT OPERATIONS CHART Amendment No. 48, Unit 2 Figure 15.6.2-2
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l Treasurer Executive Vice President
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Superintendent System Security & Fire Protection Superintendent of Insurance and Claims (NEL-PIA and NHL)
System Fire Protection Officer Director - Nuclear Power Department i
i Fire Insurance Consultants, l
Superintendent Designers &
g Nuclear Projects Office Inspectors Manager -
Nuclear Operations Point Beach Nuclear Plant Fire Protection Design Consultant WISCONSIN ELECTRIC POWER COMPANY.
0FF-SITE MANAGEMENT FIRE PROTECTION ORGANIZATION
- - - Administrative Organization FIGURE 15.6.2-3 Fire Protection Organization Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
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POINT BEACH NUCLEAR PLAPIT FIRE PROTECTION ORGANIZATION Figure 15.6.2-4 Manager -
Nuclear Operations, PBNP
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Superintendent -
Security Supervisor Operations j
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Fire Protection Supervisor Training Supervisor I
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Fire Brigade Chiefs (5) g (Operations Supervisors - 1 I
per shift)
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Asst. Fire Brigade Chiefs (5)
Two Creeks Volunteer I
(Operations Supervisors - 1 Fire Department l
per shift)
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l Contract Security Guards Operations' Brigades (1-per shift)
(25 members total)
- - - - Administrative Organization
-(Brigade Member)
Fire Protection Organization Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
15.6.3 racility Staff Qualifications 15.6.3.1 Each membdr of the f acility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
15.6.3.2 Except as provided in 15.6.3.3, either the Radicchemical Engineer or the Health Physicist shall meet the following requirements:
The individual shall have a bachelor's degree or the equivalent a.
in a science or engineering subject, including scme formal training in radiation protection.
For purposes of this paragraph, " equivalent" is as follows:
(1) Four years of formal schooling in science or engineering; or i
(2) Four years of applied radiation protection experience at a nuclear facility; or
,(3) Four years of operational or technical experience or training in nuclear powers or (4) Any combination of the above totalling four years.
b.
Except as provided in d., below, the individual shall have at least five years of profes'sional experience in applied radiation protection. A master's degree in a related field is equivalent to one year of experience and a doctor's degree in a related field is equivalent to two years of experience.
Except as provided in d., below, at least three of the five years c.
of experience shall be in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power plants.
d.
If the individual has a bachelor's degree specifically in health physics, radiological health, or radiation protection, at least three years of professional experience is required; if the individual has a master's or a doctor.'s degree specifically in health physics, radiological health, or radiation protection, at least two years of professicnal experience is required.
This experience shall be in applied radiation protection in a nuclear facility dealing with radiological prcblems similar to those enceuntered in nuclear pcuer plants.
In the event the pcsition of Radicchemical Engineer or Health Physicist 15.6.3.3 is vacated and neither the remaining individual ner the preposed replace-meets the qualifications of 15.6.3.2, but ene of these individuals
=en is deterr.ined to be otherwise well qualified, then cencurrence cf ' RC shall be sought in apprcving the qualificatien of that individual.
15.6.3-1 Ame3dment No. 43, Unit 1 Amendment No. 48, Unit 2
15.6.4 TRAINING 15.6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
15.6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Fire Protection Supervisor and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976, except that the meeting frequency may be quarterly.
15.6.5 REVIEW AND AUDIT 15.6.5.1 Duty and Call Superintendents a.
To assist and counsel the Shift Supervisor in case of significant operating events, a Duty and Call Superintendent Group has been established. The Duty and Call Superintendent Group shall consist of any qualified person designated by the Manager - Nuclear Operations.
b.
In the event of a reportable occurrence, the Shift Supervisor shall communicate with at least one Duty and Call Superintendent before taking other than the immediate on-the-spot action required.
One Duty and Call Superintendent will be assigned to be "on call" at all times. The Duty and Call Superintendent provides continuously available counsel, call out backups, and review to the Shift Supervisor.
15.6.5.2 Manager's Supervisory Staff FUNCTION 15.6.5.2.1 The Manager's Supervisory Staff 04SS) shall function to advise the Manager - Nuclear Operations on all matters related to nuclear safety.
15.6.4/5-1 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
COMPOSITION I
i 15.6.5.2.2 The Manager's Supervisory Staff shall be composed of the l
Chairman: Manager - Nuclear Operations Member Superintendent - Operations Member Superintendent - Maintenance & Construction Member:
Instrument and Control Engineer Member Superintendent - Technical Services i
i Member:
Radiochemical Engineer Member:
Health Physicist Member Assistant to the Manager - Nuclear Operations ALTERNATES t
15.6.5.2.3 Alternate members shall be appointed in writing by the MSS i
Chairman to serve on a temporary basis; however, no more than two alternates shall participate in MSS activities at any one time.
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MEETING FREQUENCY l
I 15.6.5.2.4 The MSS shall meet at least once per calendar month and as i
convened by the MSS Chairman.
QUORUM 15.6.5.2.5 A quorum of the MSS shall consist of the Chairman and four mem-bers including alternates.
RESPONSIBILITIES 15.6.5.2.6 The Manager's Supervisory Staff shall:
a)
Review existing and proposed normal, abnormal and emergency operating procedures. Review maintenance procedures and 3
proposed changes to these procedures and other procedures l
or changes thereto as determined by the Manager to affect plant operational safety.
(Re:
Section 15.6.7 for area of l
review.)
l 15.6.5-2 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
b) Review all proposed tests and experiments related to safety and the results thereof when applicable.
c) Review all proposed changes to Technical Specifications.
d) Review all proposed changes or modifications to plant systems or equipment where changes would require a change in operating or emergency procedures or that affect nuclear safety.
e) Periodically review plant operations for industrial and nuclear safety hazards.
f)
Investigate violations or suspected violations of Technical Specifications, such investigatioas to include reports, evaluations, and recommendations to prevent recurrence, to the Executive Vice President and to the Chairman of the off-site Review Committee.
i g) perform special reviews and investigations and prepare reports i
thereon as requested by the Chairman of the Off-Site Review Committee.
h)
Investigate, review, and report on all reportable occurrences.
- 1) Cause to be conducted periodic drills on emergency procedures, including evacuation (partial or complete) of the site and check adequacy of communications with off-site support groups.
j)
Review the Facility Fire Protection Program and implementing procedures at least once per 24 months.
AUTHORITY 15.6.5.2.7 a) The Supervisory Staff shall serve as advisory to the Manager -
Nuclear Operations, b)
The Supervisory Staff shall recommend to the Manager approval or disapproval of proposals under items a) through d) above.
In the event of disagreement between a majority of the Amendment No. 43, Unit 1 15.6.5-3 Amendment No. 48, Unit 2
Supervisory Staff and decisions by the Manager, the course of action will be deter.'ned by the Manager and the dis-agreement recorded in the Staff minutes.
Records of the disagreement will be included in the minutes sent for review to the Off-site Review Committee and the Executive Vice President.
c) The Supervisory Staff shall make tentative recommendations as to whether or not proposals considered by the Staff involve unreviewed safety questions.
These recommendations shall be subject to review and further recommendations by the off-site i
Review Committee. Minutes shall be kept of all meetings of the Staff and copies shall be sent to the Executive Vice President and to the Chairman of the Off-Site Review Committee.
d) The Supervisory Staff shall review and approve the contents of a report for each reportable occurrence. This report shall include an evaluation of the cause of the occurrence and recommendations for appropriate action to prevent or reduce the probability of a recurrence. Copies of all such reports shall be submitted to the Executive Vice President and to the Off-Site i
Review Committee.
r RECORDS 15.6.5.2.8 The Manager's Supervisory Staff shall maintain written minutes of each meeting and copies shall be provided to the Executive Vice President and Chairman, Off-Site Review Committee.
15.6.5-4 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
1.,. s. 5. 3 OFF-SITE REVIEW COMMITTEE (OSRC)
FUNCTION 15.6.5.3.1 The Of f-Site Review Committee 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 h) quality assurance practices i) environmental monitoring COMPOSITION 15.6.5.3.2 The Off-Site Review Committee is made up of a minimum of five regular members appointed by the Executive Vice President and one ex-officio member. Of the five or more regular members, at least two will be persons not directly employed by the Licensee. All members will be experienced in one or more aspects of the nuclear industry. The ex-officio member will be the Executive Vice President.
ALTERNATES 15.6.5.3.3 Alternate members may be appointed in writing by the OSRC Chairman to serve on a temporary basis; however, no more than two alternates shall l
l participate in OSRC activities at any one time.
CONSULTANTS 15.6.5.3.4 Consultants shall be utilized as determined by the OSRC Chairman to provide expert. advice to the OSRC.
15.6.5-5 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
MITTING FRIX)Ul:NCY 15.6.5.3.5 The OSRC shall meet at least once per calendar cuarter durinq the initial year of facility operation following fuel loading and at least twice per year at approximately six month intervals thereaf ter.
QUORUM 15.6.5.1.6 A quorum of OSRC shall consist of the Chairman or his desio-nated alternate and three members. No more than a minority of the quorum shall have line responsibility for operation of the facility.
REVIEW 15.6.5.3.7 The OSRC shall reviews a) The safety evaluations for 1) changes to procedures, equipment or systems, and 2) tests or experiments com-pleted under the provision of 10 CFR, Section 50.54, to verify that such actions did not constitute an unreviewed safety question.
b)
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR, Section 50.59.
c)
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR Section 50.59 d)
Proposed changes in Technical Specifications or Licenses.
e) Violations of applicable statutes, codes, roqnlations, orders, Technical Specifications, license requirenontn, or of internal procedures or instructions havinq nuclear safety significance.
f)
Significant operating abnormalities or deviat ions from normal and expected performance of plant equipment that af fect nuclear safety.
g)
Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notificat ion to the Commission.
August 2, 1976 15.6.5-6 Unit 1 Amendment tio.19 Uni t 2 Amendment tio. 24
I h)
Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
i)
Reports and meeting minutes of the Manager's Supervisory Staff.
AUDITS 15.6.5.3.8 Audits of facility activities shall be performed under the cognizance of the OSRC.
These audits shall encompass:
a) The conformance of facility operation to provisions contained within the Technical Specifications and appli-cable license conditions at least once per year.
b) The performance, training and qualifications of the licensed operating staff at least once per year, c) The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least twice per year at approximately six month intervals, d) The results of quarterly audits by the Quality Assurance Division on the performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per two years.
e)
Emergency Plan and implementing procedures at least once per two years.
f) Any other area of facility operation considered appropriate by the Executive Vice President.
AUTHORITY 15.6.5.3.9 The OSRC shall report to and advise the Executive Vice President on those areas of responsibility specified in Section 15.6.5.3.7 and
(
15.6.5.3.8 15.6.5-7 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
RECORDS 15.6.5.3.10 Records of OSRC activities shall be prepared, approved and distributed as indicated below:
a) Minutes of each OSRC meeting shall be prepared, approved and forwarded to the Executive Vice President within 14 days following each meeting.
b)
Reports of reviews encompassed by Section 15.6.5.3.7.e, f and g above, shall be prepared, approved and forwarded to the i
Executive Vice President within 14 days following com-pletion of the review.
c) Audit reports encompassed by Section 15.6.5.3.8 above, shall i
be forwarded to the Executive Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit.
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15.6.5-8 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
15.6.6 REPORTABLE OCCURRENCE ACTION r
Specification The following action shall be taken for REPORTABLE OCCURRENCES A.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 15.6.9.2.
B.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the Manager's Supervisory Staff (MSS) and submitted to the Off-Site Review Committee (OSRC) and the Executive Vice President.
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15.6.6-1 Amendment No. 43, Unit 1 Amendment No. 48,. Unit 2
ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED 15.6.7 Specification If a safety limit is exceeded, the affected reactor shall be shut A.
down and reactor operatics shall not be resumed until approval is received from the NRC.
An immediate report shall be made to the Executive Vice President B.
the Chairman of the Off-Site Review Committee.
and.
The Executive Vice President shall report the circumstances to the C.
NRC.
A Safety Limit Violation Report including a complete analysis of D.
the circumstances leading to and resulting from the occurrence,
'ffects upon facility components, systems or structures, together with This ommendations to prevent a recurrence, shall be prepared.
s:
report shall be submitted to the Executive Vice President and the Chairman of the Off-Site Review Committee. A Safety Limit Violation Report shall be submitted to the NRC by the Executive Vice President within 10 days of the occurrence.
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Amendment No. 43, Unit 1 15.6.7-1 i
Amendment No. 48, Unit 2
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15.6.8 PLANT OPERATING PROCEDURES 15.6.8.1 The plant shall be operated and maintained in accordance with approved procedures. Major procedures, supported by appropriate minor _ procedures (such as checkoff lists, operating instructions, data sheets, alarm responses, chemistry analytical procedures, etc.) shall be provided for the following operations where these operations involve nuclear safety of the plant:
i 1.
Normal sequences of startup, operation and shutdown of components, systems and overall plant.
2.
Refueling.
3.
Specific and foreseen potential malfunctions of systems or components including abnormal reactivity changes.
4.
Security Plan Implementation.
5.
Emergencies which could involve release of radioactivity.
6.
Nuclear core testing.
7 Surveillance and Testing of safety related equipment.
8.
Fire Protection Implementation (to be provided by March 31, 1978).
15.6.8.2 Approval of Procedures r
A.
All major procedures of the categoried listed in 15.6.8.1 (except 15.6.8.1.4) and 15.6.11, and modifications to the intent thereof, shall be i
reviewed by the Manager's Supervisory Staff and approved by the Manager -
Nuclear Operations prior to implementation.
B.
Minor procedures (checkoff lists, operating instructions, data sheets, alarm responses, chemistry analytical procedures, technical instructions, special i
and routine maintenance procedures, laboratory manuals, etc.) shall, prior to initial use, be reviewed by the Manager's Supervisory Staff and approved by the Manager - Nuclear Operations.
15.6.8-1 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
i 15.6.8.3 Changes to Procedures A.
Teaporary changes to major procedures, of the categories listed in 15.6.8.1 (except 15.6.8.1.4) and 15.6.11.1, which do not change the intent of the original or subsequent apprvved procedure, may be made provided such changes to operating procedures are approved by the Duty Shift Supervisor and one of the Duty and Call Superintendents. For temporary changes to major procedures under the jurisdiction of Maintenance, Instrumentation and Control, Reactor Engineering, or Chemistry and Health Physics which do not change the intent, changes may be made upon approval of the cognizant group head and a Duty and Call Superintendent. All Temporary changes to major procedures (made by a Duty and Call Superintendent and either a cognizant group head or the Duty shift Supervisor) shall subsequently be reviewed by the Manager's Supervisory Staff and approved by the Manager - Nuclear Operations within 2 weeks except that temporary changes to major procedure made to a given unit during its refueling outage may be reviewed and approved at any time prior to initial criticality of the reload core; and shall only become permanent changes after the Manager's Supervisory Staff's 1
review and Manager's approval steps.
B.
All temporary or permanent changes to minor operating procedures (checkoff lists, alarm responses, data sheets, operating instruc-l tions, etc.) shall be approved by the Duty Shift Supervisor, and shall be subsequently reviewed and approved by the Superintendent - Operations. All temporary or permanent changes Amendment No. 43, Unit 1 15.6.8-2 Amendment No. 48, Unit 2
I l
l to other minor procedures under the jurisdiction of Maintenance, l
r Instrumentation and Control, Reactor Engineering, er Chemistry l
and Health Physics, shall be approved by a supervisor of the j
i cognizant group and shall be subsequently reviewed and approved i
by the group head of the cognizant group.
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l i-I t
i 15.6.8-3 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2 i
15.6.9 PLANT REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following program for reporting of operating information shall be followed.
Reports should be addressed to the Director, Office of Inspection and Enforcement, I
Region III unless otherwise noted.
15.6.9.1 Routine Reports A.
Startup Report 1.
A summary report of plant startup and power escalation testing which addresses each of the tests identified in the FFDSAR and includes a general description of the measured values obtained during the test program and a comparison of these values with design predictions and specifications must be submitted under the following conditions:
Receipt of an operating license.
a.
b.
Amendment to the license involving a planned increase in power level.
Installation of fuel that has a different c.
s design or has been manufactured by a different fuel supplier.
d.
Modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
Any corrective actions that were required to obtain satisfactory operations shall also be described.
2.
This report shall be submitted within the earliest time frame of the following:
15.6.9-1 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2
9.
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a' manner less conservative than that assumed in the accident analyses in the safety analysis report or technical specifica-tions bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
B.
Thirty-Day Written Reports The types of events listed in items 1 through 4 below have lesser immediate importance. These events shall be the subject of written reports to the Director, Office of Inspection and Enforcement, Region III within 30 days of the occurrence of the event. The written report shall include, as a minimum, a completed copy of the licensee event report form, and may be supplemented, as needed to provide complete explanation of the circumstances surrounding the event.
1.
Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
2.
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required l
by a limiting condition for operation.
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l 15.6.9-6 Amendment No. 43, Unit 1 Amendment No. 48, Unit 2