ML20079P660
| ML20079P660 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/29/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079P663 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9111130133 | |
| Download: ML20079P660 (11) | |
Text
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION y
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DUKE POWER COMPANY DOCKET NO. 50 369 McGillRE htlCLEAR STATION, UNIT 1 AMENDHENT TO FACILITY OPERATING LICENSE J
Amendment No. 126 License No. NPF-9 1.
The Nuclear Regulatory Comission (the_ Comission) has found that:
The app (lication for amendment to the licGuire Nuclear Stationthe facility) Facility A.
Unit 1 by the Duke Power Company (the licensee) dated August.fi, 1991, as supplemented October 2,1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 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, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the' activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be condusted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; 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.
'h1130133911029 p
ADOCK 05000369 -
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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(P) of Facility Operating License No. NPF-9 is hereby
' amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.126, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCl. EAR REGULATORY COMfilS$10fl st i
by K
David B. Matthews, Director Project Directorate !!-3 Division of Reactor Projects-1/II
+
Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance:
October 29, 1991 A_____,,_-_.___.-_.____-__-_.-__-._.------------
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DUKE p0WER COMPANY 00CKET NO. 50 370 McGU1RE NUCLEAR STATION, UNIT 2 AfiENDMENT TO FACILITY OPERATING LICENSE Amendment No.103
-License No.-NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating) License No. NPF-17 filed by the Duke Power Company (the-licensee dated August 8, 1991, as-supplemented October 2,1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 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, the provisions of the Act, and the rules and regulations of the Comission;=
C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby this amendment can be conducted without endangering.the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter it D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this' amendment is in accordance with 10 CFR Part 51 of' the Comission's regulations and all applicable requirements have been.
satisfied.
2 2.
Accordingly, the license is hereby anended by page changes to the Technical Specifications as indicated in the attachment to this license anendment, and Paragraph 2.C.(2) of Facility Operating License No. IiPF-17 is hereby arended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.108, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license ar,endment is ef fective as of its date of issuance.
FOR THE flVCLEAR REGULATORY COMMISS10fl IC WLA p -
David B. Matthews, Director U
Project Directorate 11-3 Division of Reactor Projects-1/II o
Office of fluclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
October 29. 1991 l
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ATTACHMENT,TO LICENSE AtiENDMENT NO. 126 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 TO LICENSE AMEN 0 MENT NO.108 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET No. 50-370 Replace the following pages of the Appendix "A Technical Specifications with the enclosed pancs.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Pages insert Pages X11 X11 3/4 7-18 3/4 7-18 3/4 7-18s 3/4 7-18b 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 i
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i IkDEX LIMITING CONDITIONS FOR OPERATION AhL SURVE!LL_ANCE REOUIREMENTS LECTION PARE 3/4.7.5 STANDBY NLCLEAR SERVICE WATER PCND................
3/4 7-12 1
3/4.7.6 CONTROL AREA VEhTILATION SYSTrM..........................
3/4 7-13 3/4.7.7 AUXILIARY BUILDING FILTERED NEkTILA110N EXHAUST SYSTEM...
3/4 7-16 3/4.7.8 SNUBBERS.................................................
3/4 7-18 g
1ABLE 4.7-2 SNUBCER VISUAL INSPECT 10N INTERVAL.....................
3/4 7-18a l
FIGURE 4.7-1 SAMPLikG PLAN FOR ShuBBER FUNCTIONAL TEST...........
3/4 7-29 3/4.7.9 SEALED SOURCE CONTAMINATION..............................
3/4 7-30 3/4.7.10 Deletea 3/4.7.11 Deleted O
3/4/7.12 AREA TEMPERATURE MONIT0RlNG...............................
3/4 7-42 TABLE 3.7-6 APEA 1EMPERATURE M0NITORING............................
3/4 7-43 3/4.7.13 GR0bNDWATER LEVEL........................
3/4 7-44 TABLE 3.7-7 AUX 1LIARY BUILDING GROUNEKATER LEVEL MONITORS..........
3/4 7-45 3/4.8 ELECTRICAL POWER SYSTLMS 3/4.6.1 A.C. SOURCES Operatin9................................................-
3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE......................
3/4 8-8 1
l AmendmentNo.{fl((Unit 2)
McGuire - Units 1 and 2 xii Amendment No.
Unit 1
)
PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.
The only snubbers excluded from the requirements are those installed on non-safety-related systems and then only if the failure or the failure of the system on which they are installed would not have an adverse effect on any safety-related system.
APPLICABillTY:
MODES 1, 2 3, and 4.
MODES 5 and 6 for snubbers located on systemsrequiredOPERABLEInthoseMODES.
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform en engineering evaluatien 9
per Specification 4.7.8g. on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by aerformance of the following augmented inservice inspection program and tie requirements of Specification 4.0.5.
a.
Inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity, b.
Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor cperation and may be treated independently.
Each of these categories (inaccessibleandaccessible)maybeinspectedindependentlyaccord-ing to the schedule determined by Table 4.7-2.
The visual inspection interval for each category of snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection inter-val determined using this criteria shall be based upon the previous inspection interval as established b before Amendment Nos. AE + /of. y the requirements in effect McGUIRE - UNITS 1 and 2 3/4 7-18 Amendment No.126 Unit 1 Amendment No,108 Unit 2 1
Table 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE $NUBBERS Population Column A Column B Column C i
or Category Extended Interval Repeat Interval Reduce Interval (Notes 1 and 2)
(Notet 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 0
0-1 80 0
0 2
l 100 0
1 4
i i
l 150 0
3 8
200 2
5 13 300 5
12 25 1
400 8
18 36 l
500 12 24 48 i
750 20 40 78 1000 or greater 29 56 109
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Note 1:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of uriacceptable snubbers found during that l
interval.
Snubbers may be categorized, based upon their accessi-bility during power operation, as accessible or inaccessible.
The categories may be examined separately or jointly. - However, the-licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category, Note 2:
Interpolation between population or category size and the number of unaccepteble snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes-a fractional value of unacceptable snubbers as described by interpolation.
Note 3:
If the number of unacceptable snubbe n is equal-to or less than the number in Column A, the next inspection interval may be twice the j
previous interval but not greater than 48 months.
i McGUIRE - UNITS 1 and 2
-3/4 7-18a Amendment No.126 (Unit 1)
Amendment No.108(Unit 2)
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Teble 4.7-2 (contiriuea)
SNUBEER VISUAL INSPECTICh INTERVAL i
Nute 4:
If the number of unacceptable snubbers is ecual to or less than the Column B but greater than the nurr.ber in Column A, the next inspectiori shall be the s pe as the previuus interval.
r hote 5:
If thc snubber of unacceptable snubbers is equal to or greatcr than j
the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of uriaccep-table snubbers is less then the number in Column C but greater than the nurrber in Column B, the next interval shall be reduced propor-tionally by interpolaticr, that is, thc previous interval shall be reduu d by a factor that is cne third of the ratio of the difference between the riumber of unacceptable snubbers founa curing the previcus interval and the nuir.ber in Column P, to the difference in the numbers in Columns B and C..
Note 6:
The provisiens of Specific 6 tion 4.0.2 are applicable for all inspection intervals up to and iricluding 48 rr.onths.
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McGUIRE - UNITS 1 and 2 3/4 ?-ISb Amendment No.126 Unit 1)
Amendment No.108 Unit 21 l
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SURVEILLANCE REQUIREMENTS (Continued) c.
Refueling Outage Inspections At each refueling, the systems which have the potential for a severe dynamic event, specifically, the main steam system (upstream of the main steam isolation valves) the main steam safety and power-operated relief valves and piping, auxiliary feedwater system, main steam supply to the auxiliary feedwater pump turbine, and the letdown and charging portion of the CVCS system shall be inspected to determine if there has been a severe dynamic event.
In case of a severe dynamic event, machanical snubbers in that system which experienced the event shall be inspected during the refueling outage to assure that the mechanical snubbert have freedom of movement and are not frozen u p._
The inspection shall consist of verifying freedom of motion using one of the following:
(1) manually induced snubber movement; (2) evaluation of in-place snubber piston setting; (3) stroking the mechanical snubber through its full range of travel.
If one or -
more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be. replaced or repaired before returning to power.
The requirements of Specification 4.7.8b. are independendent of the requirements of this specification.
d.
Visual Inspection Acceptance Criteria Visual inspections shall verify:
(1) that there are no visible indications of damage or impaired OHRABILITY, and (2) attachments to the foundation or supporting structure are secure.
Snubbers which appear inoperable as a result of visual inspections "shall be classified as unacceptable and may be reclassified acceptable" for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; l
l McGUIRE - UNITS 1 and 2-3/4 7-19 Amendment No.126 Amendment No.108(Unit 1)
(Unit 2)
M-N
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
Visual Inspection Acceptance Criteria (Continued) and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8f.
A hy-draulic snubber found with the fluid port uncovered and all hydraulic snubbers found connected to an inoperable common reservoir shall be classified as unacceptable and may be reclassified acceptable by functionally testing each snubber starting with the piston in the as-found setting, extending the piston rod in the tension drection.
e.
Functional Tests During the first refueling shutdown and at least once per refueling thereafter, a representative sample of snubbers shall be tested using one of the following sample plans.
The large bore steam generator hydraulic snubbers shall be treated as a separate population for func-tional test purposes.
A 10% random sample from previously untested snubbers shall be tested at least once per refueling outage until the_ entire population has been tested.
This testing cycle shall then begin anew.
For each large bore steam generator hydiaulic snubber that does not meet the functional test acceptance criteria, at least 10% of the remaining population of untested snubbers.for that testing cycle shall be tested.
The sauple plan shall be selected prior to the test period and cannot be changed during the test period.
The NRC shall be notified of the sample plan selected prior to the test period.
1)
At least 10% of the snubbers required bj Specification 3.7.8 shall be functionally tested either in piace or in a bench test.
For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.3f.l no more failures are found an additional 10% of the snubbers shall be functionally tested unti or until all snubbers have been functionally tested; or 2)
A representative sample of the snubbers required by Specifica-tion 3.7.8 shall be functionally tested in accordance with Figure 4.7-1.
"C" is the total number of snubbers found not meeting the acceptance requirements of Specification 4.7.8f (failures).
The cumulative number of snubbers tested is denot-d by "N."
Test results shall be plotted sequentially in the order of sample assignment (i.e., each snubber shall be plotted by its order in the random sample assignments, not by the order of testing).
If at any time the point plotted falls in the " Accept" region, testing c? snubbers may be terminated.
When the point plotted lies in the " Continue Testing" region additional faubbers A
shall be tested until the point falls in the Accept". Mions or all the snubbers required by Specification 3.7.8 h e b en tested.
Testing equipment failure during functional testing aay invalidate thct day s testing and allow that day's testing to resuu anew at a later time, providing all snubbers tested with the failed equipment during the day of equipment failure are retested; or McGUIRE - UNITS 1 and 2 3/4 7-20 Amendment No.126(Unit 1)
Amendment No.108(Unit 2) i
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