ML20155B711
| ML20155B711 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/06/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155B716 | List: |
| References | |
| NUDOCS 8806130307 | |
| Download: ML20155B711 (18) | |
Text
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UNITED STATES
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00CKET NO. 50-369 McGUIRE NUCLEAR STAT 10ll, UlllT 1 AMENDMENT TO FACII.lTY OPERATING LICEtlSE Amendment flo. 86 License No. NPF-9 1.
The Nuclear Regulatory Comissiore (the Comission) has found that:
The app (lication for amendment to the McGuire Nuclear Station,.the facility A.
Unit 1 by the Duke Power Company (the licensee) dated June 5,1987, as supplemented May 19, 1988, 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, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) 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 Comissien's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and securtty 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.
8806130307 080606 DR ADOCK 050 9
. 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-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 86, are hereby incorprated 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 hUCLEAR REGULATORY COMMISSION Original signed by:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/11
Attachment:
Technical Specification Changes Date of issuance:
June 6, 1988 0FFICIAL RECORD COPY LA:PD1 -3 PM:
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DUKE P0llER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendment to the McGuire Nuclear Station,the facility) Facility A.
Unit 2 by the Duke Power Company (the licensee) dated June 5,1987, as supplemented llay 19, 1988, complies with the standards and requireuents 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 (i) that the activities authorized by this aniendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted I
l in compliance with the Comission's regulations set forth in 10 CFR l
Chapter I; D.
The issuance of this amendment will not be inimical to the comon l
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 beer satisfied.
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Q ecifications as indicated in the attachments to this license amendment, anc Paragraph 2.C.(2) of Facility Operating Licen;e tio, tiPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment flo. 67, are hereby incorperated 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 Tile IlVCLEAR REGULATORY COMMiSS10ll Original signed by:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/11
Attachment:
Technical Specification Changes Date of issuance:
June 6, 1988 OFFICIAL RECORO COPY t
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ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. NPF-9 DOCKET 110. 50-369 AND TO LICENSE AMENDMEllT !!0.
FACILITY CPERATING LICENSE N0. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are iden'.ified-by Amendment number and contain vertical lines indicating the areas of change. The corresponding over-leaf pages are also provided to maintain document corapleteness.
Amended Page Overleaf Page 3/4 7-18 3/4 7-17 3/4 7-20 3/4 7-21 3/4 7-22 3/4 7 3/4 7-24 3/4 7-25 3/4 7-26 3/4 7-27 3/4 7-28 6-23 8 3/4 7-5 l
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4 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2)
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, far a methyl iodide penetration of less than 1%; and 3)
Verifyi..g a system flow rate of 54,000 cfm i 10% (both fans operating - Unit 1) or 43,000 cfm 1 10% (both fans operating -
Unit 2) during system operation when tested in accordance with ANSI N510-1975.
c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, within 31 days af ter removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, vor a methyl iodide penetration of less than 1%;
d.
At least once per 18 months, by:
1)
Verifyina that the pressure drop across the combined HEPA filters and charcoal adsorber banks of less than 6 inches Water Gauge while operating the system at a flow rate of 54,000 cfm i 10% (both fans operating - Unit 1) or 43,000 cfm +
10% (both fans operating - Unit 2), and 2)
Verifying that the system starts on a Safety Injection test signal and directs its exhaust flow through the HEPA filters and charcoal adsorbers.
e.
After each complete or partial replacement of a HEPA filter bank, by verifying that the HEPA filter bank satisfies the in place penetration and bypass leakage testing criteria of less than 1% in accordance with ANSI N510-1975 for a 00P test aerosol while operating the system at a flow rate of 54,000 cfm i 10% (both fans operating - Unit 1) or 43,000 cfm + 10% (both fans operating - Unit 2); and f.
After each complete or partial replacement of a charcoal adsorber bank, by verifying that the charcoal adsorber satisfies the in place penetration and bypass leakage testing acceptance criteria of lee; than 1% in accordance with ANSI N510-1975 for a halogenated hydro-carbon refrigerant test gas while operating the system at a flow rate of 54,000 cfm i 10% (both fans operating - Unit 1) or 43,000 cfm 110%
(both fans operating - Unit 2).
McGUIRE - UNITS 1 and 2 3/4 7-17
PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8 All sr.ubbers shall be OPERABLE.
The only snubbers excluded from the requirements tre 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.
APPLICARILITY:
MODES 1, 2, 3. and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
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 an engineering evaluation per Specification 4.7.8g. on the attached component or declare the attached system inoperable and fcilow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Inspection Types As used in this srecification, type of snubber shall mean snubbers of the same desig,. and manufacturer, irrespective of capacity.
b.
Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation and may be treated independently.
The accessibility of each snubber shall be determined and approved by the Station Health Physicist or qualified designee prior to performing each visual inspection.
The determination shall be based upon the then existing radiation levels in each snubber location and the expected time to perform the visual inspection and shall be in accordance with the recommendations of Regulatory Guides 8.8 and 8.10.
The first inservice visual inspection of each type of snubber shall be performed af ter 4 months but within 10 months of commencing POWER OPERATION and shall include all snubbers.
If less than two snubbers l
of each type are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months i 25% from the date of the first inspection.
Othe rwi se, subsequent visual inspections shall be performed in accordance with the following schedule:
McGUIRE - UNITS 1 and 2 3/4 7-18 Amendment No. 86 (Unit 1)
Amendment No. 67 (Unit 2)
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.
When a fluid port of a hydraulic snubber is found to be uncovered the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing unless the test is started with the piston in the as-found setting, extending the piston rod in the tension mode direc-tion.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers, e.
Functional Tests During the first refueling shutdown and at least once per refueling thereaf ter, 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 shali 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 hydraulic 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 sample 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 19% of the snubbers required by Specification 3.7.8 shall be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8f., an additional 10% of the snubbers shall be functionally tested until no more failures are found or untiI all snubbers have been functionally tested; or 2)
A representative sample of the snubbers required by Specifica-tior 3.7.8 shall be functionally tested in accordance with Ficure 4.7-1.
"C" is the total number of snubbers found not meating the acceptance requirements of Specification 4.7.8f (tailures).
The cumulative number of snubbers tested is denoted ty "N."
Test results shall be plotted sequentially in the order af 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 of snubbers may be terminated.
When the point plotted lies in the "Continue Testing" region, additional snubbers shall be tested until the point falls in the "Accept" region, or all the snubbers required by Specification 3.7.8 have been tested.
Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume 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. 86(Unit 1)
Amendment No. 67(Unit 2)
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.
Functional Tests (Continued) 3)
An initial representative sample of fifty-five (55) snubbers shall be fur.ctionally tested.
For each snubber which does not-meet the functional test acceptance criteria, another sample of at least one-half the size of the initial sample shall be tested until the total number tested is equal to the initial sample size multiplied by the factor, 1 + C/2, where "C" is the number of snubbers found which do not meet the func.tional test acceptance criteria.
This plan be plotted using an "Accept" line which follows the equation N = 53(1 + C/2).
Each snubber should be plotted as soon as it is tested.
If the point plotted falls on or below the "Accept" line, testing may be discontinued.
If the point plotted falls above the "Accept" line, testing must continue unless all snubbers have been tested.
The representative samples for the functional test sample plans shall be randomly selected from the snubbers required by Specifi-cation 3.7.8 and reviewed before beginning the testing.
The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of sizes, and capacities.
Snubbers placed in the same locations as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in the sample plan.
If during the functional testing, additional sampling is required due to failure of only one type of snubber, the functional testing results shall be reviewed at that time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.
f.
Functional Test Acceptance Criteria The snt.sber functional test shall verify that:
1)
Activation (restraining action) is achieved within the j
specified range in both tension and compression, except that l
inertia dependent, acceleration limiting mechanical snubbers may be tested to verify only that activation takes place in both directions of travel; l
2)
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range; 3)
Where required, the force required to initiate or maintain motion of the snubber is within the specified range in both direction of travel; and 4)
For snubbers specifically required not to displace under I
continuous load, the ability of the snubber to withstand load without displacement.
l Testing methods may be used to measure parameters indirectly or I
parameters other than those specified if those results can be correlated to the specified parameters through established methods.
McGUIRE - UNITS 1 and 2 3/4 7-21 Amendment No. 86 (Unit 1) l Amendment No. 67 (Unit 2)
I
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) g.
Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure.
The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type which may be subject to the same failure mode.
For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached.
The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.
If any snubber selected for functional testing either fails to activate or fails to move, i.e., frozen-in place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be evaluated in a manner to ensure their OPERABILITY.
This testing requirement shall be independent of the requirements stated in Specification 4 7.8e.
for snubbers not meeting the functional test acceptance criteria.
h.
Functional Testing of Repaired and Rer b ;ed Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have repairs which might affect the functional test result shall be tested to meet the functional test criteria before installation in the unit.
Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent service, and freedom-of-motion test must have been performed within 12 months before being installed in the unit.
i.
Snubber Seal Replacement Program The seal service life of hydraulic snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections.
The expected service life for the various seals, seal materials, and applications shall be determined and established based en engineering information and the seals shall be replaced so that the expected service life will not be exceeded during a period when the snubber is required to be OPERABLE.
The seal replacements shall be documented and the documentation shall be retained in accordance with Specification 6.10.2.
McGUIRE - UNITS 1 and 2 3/4 7-22 Amendment No. 86(Unit 1) l Amendment No. 67(Unit 2)
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Amendment No.67 (Unit 2)
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Amendment No. 67 (Unit 2) w
ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) g.
Records of training and qualification for current men.bers of the unit staff; h.
Records of liiservice inspections performed pursuant to these Technical Specifications; i.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuont to 10 CFR 50.59; j.
Records of meetings of the NSRB and reports required by Specification 6.5.1.12; k.
Records of the service lives of all snubbers including the date at l
which the service life commences and associated installation and maintenance records; 1.
Records of secondary water sampling and water quality; and m.
Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.
This should include procedures effective at specified times and QA records showing that these procedures were followed.
6.10.3 Records of quality assurance activities required by the QA Manual shall be retained for a period of time required by ANSI N45.2.9-1974.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mrem /hr at 45 CM (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RVP).
Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel cortin-uously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mrem /hr provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
McGUIRE - UNITS 1 and 2 6-23 Amendment No. 86 (Unit 1)
Amendment No. 67 (Unit 2)
PLANT SYSTEMS BASES 3/4.7.8 SNUBBERS All squbbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all othe-safety related systems is maintained during and following a seismic or other event initiating Jynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
Snubbers are classified and grouped by design and manufacturer but not by size.
For exarple, mechanical snubhers utilizing the same design features of the 2 kip,10 kip, and 100 kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured Company "B" for the pur.ases of this specificstion would be of a different type, as would hydraulic snubbers from either manufacturer.
Tha visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers fcund during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
To provide assurance of snubber functional reliability one of the three sampling and acceptance criteria methods are used:
1.
Functionally test 10% of a type of snubber with an additional 10%
tested for each tunctional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or continue testing
- using Figure 4.7-1, or 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated eouation.
Figure 4.7-1 was developed using "Wald's Sequential Probability Ratio Plan" as described ir. "Quality Control and Industrial Statistics" by Acheson J. Duncan.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubter life destructive testing was performed to qualify the snubber for the applicable design conditions at either the l
completion of their fabrication or at a subsequent date.
t
^If testing continues to between 100-200 snubbers (or 1-2 weeks) and still the accept region has not been reached, then the actual % of population quality (C/N) should be used to prepare for extended or 100% testing.
l McGuire - UNITS 1 and 2 8 3/4 7-5 Amendment No. 86 (Unit 1)
Amendment No. 67 (Unit 2)
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