ML20236E528
| ML20236E528 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/06/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236E530 | List: |
| References | |
| NUDOCS 8906150023 | |
| Download: ML20236E528 (20) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 5
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WASHINGTON, D. C. 20555
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DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 i
ARENDMEh110 FACIL11Y OPERATING LICENSE H
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Amendment No. 98 License No. NPF-9 1
l 1.
The Nuclear Regulatory Comission (the Comission) has found that:.
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A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated March 9,1987, as revised March 20 and May 19 and 23,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 1
Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as i
anended, the provisions of the Act, and the rules and regulations
~
of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and I
safety of the public, end (ii) that such activities will be conductec in compliance with the Comission's regulations set forth in 10 CFR I
Chapter I; l
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.
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8906150023 890606 gDR ADOCK0500g9 l
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. 2.
Accordingly, the license is hereby amended by page changes to the Technical i
Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Focility Operating License No. NPF-9 is hereby -
amended to read as follows:
(2) Tedinical $pec1iications 1
The Technical Specifications contained in Appendix A, as revised through Amendment No. 93, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the--
Technical Specifications and the Environmental Protection Plan.
l
'I 3.
Facility Operating License NPF-9 'is further amended as follows:
A.
Change license condition 2.C.(4) to read as follows:
)
(4) Fire Protection i
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Duke Power Company shall implement and maintain in effect all I
provisions of the approved fire protection program as described
)
in the Final Safety Anelysis Report, as updated, for the facility through the.1989 annual FSAR update and as approved in the SER j
dated March 1978 and Supplements 2, 5 and 6 dated March 1979, April 1981, and February 1983, respectively, and the safety
)
evaluation dated May 15, 1989, subject to the following provision:
1 The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effectiva as of its date of issuance and shall be implemented within 30 days of issuance.
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FOR THE NUCLEAR REGULATORY C0!911SS10N h
M avid B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: June 6, 1989 l
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2.
Accordingly, the license is hereby amended by page changes to the Technical 1
Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby l
anended to read as follows:
(2) Technical Specifications l
i The Technical Specifications contained in Appendix A, as revised
~
through Amendment No. 98, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the 1
Technical Specifications and the Environmental Protection Plan.
_l i
3.
Facility Operating License NPF-9 is further amended as follows:
A.
Change license condition 2.C.(4) to read as follows:
(4) Fire Protection Program Duke Power Company shall implement and maintain in effect all l
provisions of the approved fire protection program as described
]
in the Final Safety Analysis Report, as updated, for the facility through the 1989 annual FSAR update and as approved in the SER dated March 1978 and Supplements 2, 5 and 6 dated March 1979, l
April 1981, and February 1983, respectively, and the safety evaluation dated May 15, 1989, subject to the following provision:
The licensee may make changes to the approved fire protection i
program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of'a fire.
4.
This license amendrent is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION On inal Signed By'-
s David B. Matthews i
David B. Matthews, Director l
l Project Directorate 11-3 Division of Reactor Projects-I/II j
Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
June 6,1989
- See previous concurrence PDII-3 PDIl-3 ECEB OGC-WF PDII-3 MRood
- DHood:1s
- CMCCrachen
- NRomney*
DMatthews 3
05/ 489 05/ /69 05/ 25'89 05/25 /S9 05A5 /89
k,.
l, Accordingly, the license 11s herebyl amended by;page changes to the Technical
-Specifications as indicated in the attachments to this'11 cense amendment,,
and Paragraph 2.C.(2) of Facility' Operating License No. NPF-9 is hereby 1
mended to read as follows:~
s (2
Technical Specifications-e Technical Specifications contained in Appendix A, as revised t
ugh Amendment No.
, are hereby. incorporated into the license.
The icensee shall operate the facility in accordance with the; Tech cal Specifications and the Environmental Protection Plan'.
I 3.
Facility Ope ing License NPF-9 is further amended a's follows:
A.
Change lic recondition 2.C.(4)_to'readasfollows:
(4). Fire Prot. tion
'a Duke Power any shall implement'and maintain in.effect all provisions of he app ~aved fire protection program as-described in the Final Sa ty Analysis Report, as updated, for the facility-through the 1989 nual FSAR update and as ~ approved in the SER dated March 1978 Supplements > 2,- 5. and 6 dated March 1979, April 1981, and February 1983,_ respectively, and the safety evaluation dated May 15,1989, subject to the following, provision:-
The licensee may'make cKanges to the approved fire protection program without prior approval of the Commission only if those changes would not adverseiy affect the ability to achieve and l
maintainsafeshutdownintheeventofa' fire.
4 This license amendment is effective as t-date of~1ssuance.
N FOR THE nd14AR REGULATORY COMMISSION 1
-I l-David B: Matthews,' Director i
Project Directorate Ib3 Divisionof:ReactorProhcts-1/II 0
1 Office of. Nuclear. Reactor \\ egulation E
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Attachment:
Technical Specification l
l Changes i
Date of Issuance:.
4 ECEB OGC-W M PDII-3' PD 1.h 3
PD i
5 DHood:1s CMCCr ken NRosas.+
DMatthews
.i 05/J,N89 05/ $/89 05/
89 05/30/89 05/ t/89
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UNITED STAT ES g
NUCLEAR REGULATORY COMMISSION 7,
-p WASHINGTON, D. C. 20555
.+ /
DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO F,ACILITY OPERATING LICENSE Amendment No. 80 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The app (lication for amendment to the McGuire Nuclear Station,the facility)
Unit 2 by the Duka Power Company (the licensee) dated March 9, 1987, as revised March 20 and May 19 and 23,1989, conplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations set forth in 10 CFR Chapter I; 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 anendment 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 hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 80, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
Facility Operating License NPF-17 is further amended as follows:
A.
Change license condition 2.C.(7) to read as follows:
(7) Fire Protection Duke Power Company shall implement and maintain in effect all-provisions of the approved fire protection program as described in the Final Safety Analysis Report, as updated, for the facility through'the 1989 annual FSAR update and as approved in the SER dated March 1978 and Supplements 2, 5 and 6 dated March 1979, April 1981, and February 1983, respectively, and the safety evaluation dated May 15, 1989, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY C0tHISSION f
David B. Matthews, Director 0
Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
June 6, 1989
)
I
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of facility Operating License No. NPF-17 is hereby emended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 80, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
Facility Operating License NPF-17 is further amended as follows:
A.
Change license condition 2.C.(7) to read as follows:
(7) Fire Protection Duke Power Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, as updated, for the facility through the 1989 annual FSAR update and as approved in the SER dated March 1978 and Supplements 2, 5 and 6 dated March 1979, April 1981, and February 1983, respectively, and the safety evaluation dated May 15, 39S9, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
David B. Matthews David B. Matthews, Director Project Directorate 11-3 Division of Reactor. Projects-I/II Office of Nuclear Reactor Regulation i
. Attachment-Technical Specification Changes l
)
Date of Issuance:
June 6, 1989
- See previous concurrence PDII-3 PDII-3 ECEB OGC PDII-3 MRood
- DHood:ls
- CMcCracken
- NRomney*
DMatthews
- 05/ 25/89 05/2789 05/ 2W89 05/3489 05/ 31/89
. ~
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17'is hereby mended to read as follows:
(2 Technical Specifications Thq Technical Specifications contained in Appendix A, as revised thrbpgh Amendment Nu.
, are hereby incorporated into the license.
The hcensee shall operate the facility in accordance with the Technic Specifications and the Environmental Protection Plan.
3.
Facility Opera' i License NPF-17 is further amended as follows:
A.
Change licens condition F.C.(7) to read as follows:
(7) Fire Protec on Duke Power Com ny shall implement and maintain in effect all provisions of th approved fire protection program as described j
in the Final Safe Analysis Report, as updated, for the facility I
through the 1989 an 1 FSAR update and as approved in the SER j
dated March 1978 and plements 2, 5 and 6 dated March 1979, i
April 1981, and Februa 1983, respectively, and the safety.
i evaluation dated May 15, 89, subject to the following provision:
The licensee' may make cha s to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and' maintainsafeshutdownintheeYentofafire.
4.
This license amendment is effective as of i ate of issuance.
FOR THE NUCLE REGULATORY COMMISSION David B. Matthews, Direc r
. Project Directorate II-3 Division of Reactor Projec I/II Office of Nuclear Reactor Regu tion Technical Specification l
Changes l
Date of Issuance:
3hD 1
.3 PDII-3 ECEB OGC PDIl-3 l
Kit e
DHood:ls CMcCr cken N ROMM'f bDMatthews 05/13/89 05/g/89 05/$)p/89 05/3 0/89 v 05/Al/89 I
l
ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 80 FACILITY OPERATING LICENSE NO NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendnent number and contain vertical lines indicating the areas of change. The corresponding over-leaf page is also provided to maintain document completeness.
Amended Page Overleaf Page VII XII XVIII 3/4 3-58 3/4 3-59 3/4 3-60 3/4 3-61 3/4 3-62 3/4 3-63 3/4 3-64 3/4 3-65 3/4 7-32 3/4 7-33 3/4 7-34 3/4 7-35 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-39 3/4 7-40 3/4 7-41 l
6-1 1
6-9 6-14 B 3/4 3-4 8 3/4 3-3 B 3/4 7-6 B 3/4 7-7
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................
3/4 3-54 Accident Monitoring Instrumentation.......................
3/4 3-55 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................
3/4 3-56 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................
3/4 3-57 I
Radioactive Liquid Effluent Monitoring Instrumentation....
3/4 3-66 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................
3/4 3-67 TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........
3/4 3-69 Radioactive Gaseous Effluent Monitoring Instrumentation...
3/4 3-71 TABLE 3.3-13 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION...................................
3/4 3-72 TABLE 4.3-9 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........
3/4 3-75 Loose-Part Detection System..............................
3/4 3-78 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................
3/4 3-79 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation..............................
3/4 4-1 Hot Standby..............................................
3/4 4-2 Hot Shutdown.............................................
3/4 4-3 j
Cold Shutdown - Loops Fi11ed.............................
3/4 4-5 McGUIRE - UNITS 1 and 2 VII Amendment No. 98 Amendment No. 80 (Unit 1)
(Unit 2)
r.___-_.
..-u.
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.5-STANDBY NUCLEAR SERVICE WATER P0ND........................
3/4 7-12 0
3/4.7.6
. CONTROL AREA VENTILATION SYSTEM...........................
3/4 7-13 3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM...
'3/4 7-16 1
3/4.7.8 SNUBBERS.................................................
'3/4 7-18 TABLE 3.7-4a SAFETY-RELATED HYDRAULIC SNUBBERS (UNITS 1 AND 2)....
3/4 7-23 TABLE 3.7-4b' SAFETY-RELATED MECHANICAL SNUBBERS (UNITS 1 AND'2)....
3/4 7-26?
FIGURE 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST...........
'3/4:7-29' j
3/4.7.9 SEALED SOURCE CONTAMINATION................................
3/4 7-30 3/4.7.10 Deleted i
3/4.7.11 Deleted i
L 3/4/7.12 AREA TEMPERATURE MONITORING...............................
3/4 7-42 TABLE 3.7-6 AREA TEMPERATURE M0NITORING............................
3/4 7-43 3/4.7.13 GROUNDWATER LEVEL.........................................
3/4 7-44 i
TABLE 3.7-7 AUXILIARY BUILDING GROUNDWATER' LEVEL MONITORS...........
3/4 7-45 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES
'd 0perating..............................................~..
3/4 8-1 TABLE 4.B-1 DIESEL GENERATOR TEST SCHEDULE......................
3/4 8-8 i
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McGuire - Units 1 and 2 XII
. Amendment No. 98 (Unit 1)
R Amendment No. 80 (Unit 2)
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INDEX 8ASES SECTION PAGE 1
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........
B 3/4 7-3 1
3/4.7.3-COMPONENT COOLING WATER SYSTEM............................
B 3/4 7-3 1
3/4.7.4 NUCLEAR SERVICE WATER SYSTEM..............................
B 3/4 7-3
{
3/4.7.5 STANDBY NUCLEAR SERVICE WATER P0ND.........................
B 3/4 7-3a TABLE-B 3/4 7-1 NUCLEAR SERVICE WATER SYSTEM SHARED VALVES..........
B 3/4 7-3b 1
3/4.7.6 CONTROL AREA VENTILATION SYSTEM...........................
B 3/4 7-4 f
3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM....
B 3/4 7-4 1
3/4.7.8 SNUBBERS.................................................. -B 3/4 7-5 i
3/4.7.9 SEALED SOURCE CONTAMINATION...............................
B 3/4 7-6' 3/4.7.10 Deleted j
3/4.7.11 Deleted 3/4.7.12 AREA TEMPERATURE MONITORING...............................
B 3/4 7 6 j
3/4.7.13 GROUNDWATER LEVEL.........................................
B 3/4 7-6 L!
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES AND
'1 ONSITE POWER DISTRIBUTION SYSTEMS.........................
B 3/4 8-1 1
3 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...................
B 3/4 8-3 1
3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................................
B 3/4 9-1 j
3/4.9.2 INSTRUMENTATION...........................................
B 3/4 9-1 3/4.9.3 DECAY TIME.....................
B 3/4 9-1 i
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.........................
B 3/4 9-1 i
4 3/4.9.5 COMMUNICATIONS............................................
B 3/4 9-2 3/4.9.6 MANIPULATOR CRANE.........................................
B 3/4 9-2 i
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING...........
B 3/4.9-2 l
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-McGUIRE - UNITS I and 2 XVIII Amendment No. 98 (Unit 1)-
Amendment No.80 (Unit 2)
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Pages 3/4 3-58 through 3/4 3-65 deleted.'-
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McGUIRE - UNITS 1 and 2 3/4 3-58 Amendment No. 98 (Unit 1)'
Amendment No. 80 (Unit 2) l
r ic
's' PLANT SYSTEMS
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v Pages 3/4 7-32 through 3/4 7-41' deleted.:
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McGUIRE - UNITS 1 and 2 3/4 7-32 Amendment No.98 (Unit.1)'
i Amendment No.80 (Unit 2)'
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6.0 -ADMINISTRATIVE CONTROLS I
a 6.1 RESPONSIBILITY
)
6.1.1' The Station Manager shall be responsible for overall unit operation and
^
shall delegate in writing the succession to this responsibility during his absence.
I 6.1.2 The Shift Supervisor (or during his absence from the control room, a designated individual) shall be responsible for the control room command function.
A management directive to this effect, signed by the Vice-President Nuclear Production shall be reissued to all Nuclear Production Department station personnel on an annual basis..
6.2 ORGANIZATION OFFSITE l
1 6.2.1 The offsite organization for unit management and technical support shall be as described in the FSAR, Chapter 13.
UNIT STAFF 6.2.2 The unit organization shall be as shown in the FSAR, Chapter 13, and:
a.
Each on-duty shift shall be composed of at least the minimum shift i
crew composition shown in Table 6.2-1;
)
b.
At least one licensed Operator for each unit shall be-in the control room when fuel is in either reactor.
In addition, while either unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room; A Health Physics Technician # shall be on site when fuel is in either c.
reactor; i
d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibil-
)
ities during this operation; and I
- The Health Physics Technician composition may be less than the minimum l
requirements for a 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 accommo-date unexpected absence, provided immediate action is taken to fill the required positions.
McGUIRE - UNITS 1 and 2 6-1 Amendment No. 98 (Unit 1)
Amendment No. 80 (Unit 2)
ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) 6.5.1.6 ALL REPORTABLE EVENTS and all violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence.
Such reports shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Director of the Nuclear Safety Review Board.
6.5.1.7 The Station Manager shall assure the performance of special' reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Nuclear Production.
6.5.1.8 The station security program, and implementing procedures, shall be reviewed at least once per 12 months.
Recommended changes shall be approved by the Station Manager or Superintendent of Station Services and transmitted to the Vice President, Nuclear Production, and to the Director of the Nuclear Safety Review Board.
6.5.1.9 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months.
Recommended changes shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Produc-tion, and to the Director of the Nuclear Safety Review Board.
6.5.1.10 The Station Manager shall assure the performance of a review by a qualified individual / organization of every unplanned onsite release of radio-active material to the environs including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence to the Vice President, Nuclear Production and to the Nuclear Safety Review Board.
6.5.1.11 The Station Manager shall assure the performance of a review by a qualified individual / organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.
6.5.1.12 The Station Manager shall ensure the performance of a review by a qualified individut./ organization of the Fire Protection Program and implement-ing procedures and submittal of recommended changes to the Nuclear Safety Review Board.
6.5.1.13 Reports documenting each of the activities performed under Specifi-cations 6.5.1.1 through 6.5.1.12 shall be maintained.
Copies shall be provided to the Vice President, Nuclear Production, and the Nuclear Safety Review Board.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION 6.5.2.1 The NSRB 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, i
McGUIRE - UNITS I and 2 6-9 Amendment No.98(Unit 1)
Amendment No.80(Unit 2)
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)
The Safety Limit Violation Report shall be submitted to the c.
Commission, the NSRB and the Vice President, Nuclear Production, within 14 days of the violation; and d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix A of Regulatory a.
Guide 1.33, Revision 2, February 1978; b.
The applicable procedures required to implement the requirements of NUREG-0737; c.
Security Plan implementation;*
d.
Emergency Plan implementation; PROCESS CONTROL PROGRAM implementation; e.
f.
OFFSITE DOSE CALCULATION MANUAL implementation; and g.
Quality Assurance Program for effluent and environmental monitoring.
h.
Fire Protection Program implementation.
i.
Commitments contained in FSAR Chapter 16.0 6.8.2 Each procedure of Specification 6.8.1 above, and changes thereto, shall be reviewed and approved by the Station Manager; or by:
(1) the Operating Superintendent, (2) the Technical Services Superintendent, (3) the Maintenance Superintendent, or (4) the Superintendent of Integrated Scheduling as previously destynated by the Station Manager; prior to implementation and shall be reviewed periodically as sat forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8.1 above may be made provided:
The intent of the original procedure is not altered; a.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and
- Review and approval may be performed by the Superintendent of Station Services.
McGUIRE - UNITS 1 and 2 6-14 Amendment No. 98(Unit 1)
Amendment No.80(Unit 2)
.i BASES ~
3/4.3.3.1 DELETED 3/4.3.3.8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
.The radioactive liquid effluent instrumentation is provided to monitor
}
and control, as applicable, the releases of radioactive. materials-in liquid 1
effluents during actual or potential releases of liquid' effluents.
The Alarm /-
Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm / Trip will occur prior to exceeding the limits of 10 CFR Part 20.'
The' q
OPERABILITY and use of this instrumentation is consistent with the requirements 1
of General Design. Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
The purpose of tank level indicating devicesLis to assure the detection and 1
control of leaks that if not controlled could potentially result in the.
1 transport of radioactive. materials to UNRESTRICTED AREAS.
I 3/4.3.3.9 RADI0 ACTIVE GASE00S' EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor.
and control, as applicable, the releases of radioactive materials in gaseous effluents during actual. or potential releases of gaseous effluents.
The-Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters.in the ODCM to ensure that the Alarm / Trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring.(and controlling) the J
concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP-SYSTEM.
The OPERABILITY and use of this instrumentation is' consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
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McGUIRE - UNITS 1 and 2 B 3/4 3-4 Amendment No. 98(Unit 1)
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Amendment No. 80(Unit 2) l 1
BASES SNUBBERS (Continued)
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radistion area, in high temperature area, etc...).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenance of records and the snubber service life review not intended to affect plant operation.
3/4.7.9 SEALED SOURCE CONTAMINATION I
The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group.
Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.7.10 Deleted 3/4.7.11 Deleted 3/4.7.12 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures.
Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY.
The temperature limits include an allowance for instrument error of 3.9 F.
3/4.7.13 GROUNDWATER LEVEL i
l This Technical Specification is provided to ensure that groundwater levels will be monitored and prevented from rising to the potential failure limit for the McGuire Units 1 and 2 Auxiliary Buildings.
This potential failure limit is based on engineering calculations that have determined that the Auxiliary Buildings are susceptible to overturning due to buoyancy at elevation 737 feet Mean Sea Level (MSL).
Under the requirements of this Technical Specification, if groundwater level exceeds elevation 731 feet MSL, (3 out of 5 Tech Spec McGuire - UNITS 1 and 2 B 3/4 7-6 Amendment No. 98 (Unit 1)
Amendment No. 80 (Unit 2)
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BASES l
GROUNDWATER LEVEL (Continued) groundwater monitor alarms), and cannot be reduced in one (1) hour, McGuire must begin reducing Units 1 and 2 to Mode 5, Cold Shutdown.
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Analysis performed by Design Engineering determined that the' Reactor and Diesel l
Generator Buildings are designed to withstand hydrostatic-loadings due to j
groundwater levels up to elevation 760 feet MSL; therefore, no Technical 3
Specification requirements are specified for these structures.
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1 Elevation 731 feet MSL is the Technical Specification action level of the five Technical Specification groundwater monitors listed in Table 3.7-7.
The East Wall exterior monitor alarm at elevation 731 feet MSL is the Alert alarm due to the groundwater well being bored to a depth of 730 feet MSL because of under-ground rock formation below the well.
The other four'(4) monitors are'Hi-Hi-alarms at elevation 731 feet (MSL).
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The East Wall exterior monitor was originally on the exterior of tnd Unit 2 Auxiliary Building and subsequently was enclosed by the construction of the Equipment Staging Building.
1 As required by Operations procedures, any alarms on non-Technical. Specification groundwater monitors will also be investigated.
Additionally,'if three (3) out of the five (5) Technical Specification groundwater monitors alarm at~ levels i
below the Technical Specification action levels, Operations'will contact Duke Design Engineering (Civil) for investigation and resolution of the increased groundwater level.
If one or more of the 5 Technical Specification groundwater monitors is~ deter-mined to be inoperable, the monitor (s) will be considered to be indicating above the 731'-0" level until repaired and returned to an operable status.
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l McGuire - UNITS 1 and 2 B 3/4 7-7 Amendment No. 98 (Unit 1) l Amendment No. 80 (Unit 2) w-__-_-__-__.
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