ML20040G438
| ML20040G438 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/03/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040G437 | List: |
| References | |
| NUDOCS 8202160030 | |
| Download: ML20040G438 (14) | |
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3[,N UNITED STATES NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20556
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YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Yankee Atomic Electric Company (the licensee) dated September 1,1981, 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 facility 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 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 r'egulations; 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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e O202160030 820203 PDR ADOCK 05000029 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:
2.C(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 71, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3 This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Dennis M. Crutchfield, dhie Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 3,1982 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 71 FACILITY OPERATING LICENSE N0'. DPR-3 DOCKET NO. 50-29 Replace the following pages* of the Appendix "A" Technical Specifications with the enclosed pages as iridicated.
The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT VI VI XI XI 3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-28 3/4 7-29 3/4 7-29 3/4 7-29a 3/4 7-29b B3/4 7-6 B3/4 7-6 B3/4 7-6a 6-23 6-23 9
- 0verleaf page B3/4 7-5 is included for document completeness.
t INDEX LIMITING CONDITIONS FOR OPER ATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 3 COMBUSTIBLE GAS CONTROL Hydrogen Analyzer........................................
3/4 6-16 Hydroge n Vent Sys t em..................................... 3/4 6-17 Atmo s pnere Re circula tio n System..........................
3/4 6-18 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves............................................
3/4 7-1 Emergency Feedwa ter System............................... 3/4 7-5 Primary a' d Demineralized Water StoraSe Tanks............
3/,4 7-6 n
A c t i v i ty........'......................................... 3 / 4 7 -7 Mai n S tea m Non-Re t urn Val ves............................. 3 / 4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPER ATURE LIMITATION.......... 3/4 7-13 3/4.7 3 PRIMARY PUMP SEAL WATER SYSTEM (Deleted).................. 3/4 7-14 3/4.7.4 SERVICE WATER SYSTE4 (Deleted)............................ 3/4 7-16 3/4.7.5 CONTROL ROOM VENTILATION SYSIEM EMERGENCY SHUTDOWN.......
3/4 7-18 3/4.7.6 S E ALED SOUR CE CON TAMIN ATIO N.............................. 3/4 7-19 3/4.7.7 WASTE EFFLUENTS Ra di o a c t i v e Sol id Was te..................................
3 / 4 7-21 Radioa c tive Liq uid Was te................................. 3/4 7-22 Radioa ctiv e Gas eous Was te................................
3/4 7-23 3/4.7.8 ENV IRO NM ENTAL MONITORING.................................. 3/4 7-24 SNUBSERS.................................................
3/4 7-27 l
3/4.7.9 3/4.7.10 FIRE SUPPRESSION SYSTE3S.................................
3/4 7-30 3/4.7.11 PENETRATION FIRE BARRIERS................................
3/4 7-37 YANKEE-R0riE VI A=endment No. M, M, % h,
%, ps; 71
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INDEX BASES m
SECTION.
PACE 3/4.6 ' CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY C0NTAINMENI....................................... B 3/4 6-1 3/4.6.2 CONTAINMENT IS OLAT ION VALVES.............................. B 3/4 6-3 3/4.6.3 C0 tmUSTIBLE c AS CONTR0L................................... B 3 /4 6-3 3/4.7 PLANT SYSTEMS 3/4.7.1 T URB I N E C YCLE............................................. B 3 / 4 7-1 3/4.7.2 STE AM GENERATOR PRESSURE / TEMPERATURE LIMITATIONS.......... B 3/4 7-4 3/4.7.3 PRIMARY PUMP SE AL WATER SYST EM (Deleted).................. B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM (Dele te d)............................ B 3/4 7-4 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM EMERGENCY ' SHUTDOWN........ B 3/4 7-4 3/4.7.6 SEALED SOURCE CONTAMINAT ION............................... B 3/4 7-4 3/4.7.7 WAST E E FFLUENTS........................................... B 3 /4 7-5 3/4.7.8 ENVIRONMENTAL MONITO RING................................. B 3 / 4 7-6 3/4.7.9-S N UB EE R S.................................................. B 3 / 4 7 - 6 l 3/4.7.10 F IRE SUP P RES S ION SYSTEMS.................................. B 3 / 4 7-7 3/4.7.11 PE NETRA TION FIRE B AR RIERS................................. B 3 /4 7-7 3/4.8 ELECTRICAL POWER SYSTDIS 3/4.8.1 A.C. S0URCES....'..........................................
B 3/4 8-1 3/4.8.2 ONSITE. POWER DISTRIBUT ION SYSTEMS......................... S 3/ 4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 RE ACT IV ITY................................................ B 3 / 4 9 -1 3/4.9.2 I NSTRUMENTAT IO N........................................... B 3 / 4 9-1 YANKEE-ROWE XI Amendment No. 'M, y( 71
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PLANT SYSTEMS 3/4.7.9. SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers listed in Table 3.7-4 shall be OPERABLE.
AP PLICABILITY: 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 9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
, SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated CPERABLE by performance of the following augmented inservice inspection program, a.
Visual Inspections The first inservice
- visual inspection of snubbers shall be performed, af ter_ yune_ _3,1982_
but before December 3,1982 and shall include all snubbers listed in Table 3.7-4.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice, visual inspection shall be performed 12 months + 25% f rom the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the.following schedule:
No. Inoperable Snobbers Subsequent Visual p per Inspection Period Inspection Period
- O 18 months + 25%
1 12 months II 25%
2 6 months II 25%
3, 4 124 days + 25%
5,6,7 62 days +[25%
8 or more 31 days + 25%
The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance. with the above schedule.
- The inspection interval shall not be lengthened more than one step at a. time.
- The provisions of Specification 4.0.2 are not applicable.
Yankee'Rowe 3/4 7-27 knendment No. J I,71 F
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.-
Visual Inspection Acceptance Criteria Visual inspections shall> verify (1) that there are no visible' indica-
'i' tions of damage or impaired OPERABILITY, (2) attachments to the foun-dation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the ;aubber, that the snubber has freedom of movement and is not f roze n up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the"cause of the rejection is clearly established and remedied fcr that particular snubber and for the other snubbers that,may be generically suscept-ible; and (2) the af fected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.9.d.
However, when the fluid port of a hydrculic snubber is found to be
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uncovered, the snubber shall be determine ~d inoperable and cannot be determined OPERABLE via functional testing for the purpose of estab-lishing the next visual inspection inter'ral. All snubbers connected to an inoperable common hydraulic fluid reservior shall be counted as inoperable snubbers.
c."
Functioaal Tests At least once per 18 months during shutdown, a representative sample (10% of the total of each type of snubber in use in the pland 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 4.7.9.d. an additional 10% of that type of snubber shall be. functionally tested.
The representative sa=ple selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At le'a st 25% of the ' snubbers in the representative sample shall include snubbers from the following three categories:
1.
The first snubber away from each reactor vessel nozdle 2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)
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Snubbers within 10 feet of the discharge from a safety relief valve g
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Yankee Rowe 3/4 7-28 Amendment No.,4t*, 71 s
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! PLANT SYSTEMS SURVEIL ANCE REQUIREMENTS (ContinuedL f
Snubbers identified in Iable 3.7-4 as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representa?.ive sample.
Table 3.7-4 may be used jointly or separately a's the basis for the sampling plan.
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed '
snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be re tested. Test results of these snubbers may not be included for the re-sampling.
If ary snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the caus.e will be evaluated and if caused by manufacturer or design deficiency all i
snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely af fected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
d.
Mechani:al Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
1.
The f orce'that initiates free novecent of the snubber rod in either tension or compression is less than the specified m'aximum drag f orce. Drag force shall not have increased more than 50% since the last functional test.
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Yankee sRowe 3/4 7-29
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compressio n.
! I 3.
Snubber release rate, where required, is within the specified range in compreasion or tension. For snubbers specifically required not to displace under continuous load the ability of the snubber to withscand load without displacement shall be verified.
e.
Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2 m.
Concurrent with the first inservice visual inspection and at least
,once per 18 months thereaf ter, the installation and maintenance records for each snubber listed in Table 3.7-4 shall be reviewed to verif y that the indicated service life has not been exceeded or will
- not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life _ review, the snubber service life shall be reevaluated or the snubber shall be replaced or rec.onditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.
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l Yankee Rowe 3/4"7-29a Amendment No. 4I, 71
6 TABLE 3 7-4
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SAFEY RELATED MECalANICAL SNUBBEHSn E
111Gil RADIATION l
rp S:lubdEli SYSTtN SNUBBER INSTALLED ACCESSIB1.E OR ZONE ESPECIALLY DIFFICULT
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ON, LOCATION AND ELEVATION INACCESLIbl.E DURING SliUTDOWNae TO HEMOVE g
(A or 1)
(Yes or No)
(Yes or No) 1133 19A Pressurizer relief valve, A
No No 1133 1913 pressurizer cubicle A
No No lisS 20A A
No No tidS 2015 A
No No '
236 S/G No.
1, Hight side I
Yes Yes 221 S/G No.
1, Left side L
Yes Yes 44')
S/G No. 2, Right side 1
Yes Yes 441 S/G No. 2, Left side I
Yes Yes
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41 6 S/G No. 3, Hight side I
Yes Yes 1
443 S/G No. 3, Left side I
Yes Yes y
4 44'l S/U No. 4, Right side I
Yes Yes y
437 S/,G No. 4 Le f t s ide 1
Yes Yes Snubbers naay be added to safety relat.ed systems without prJoe License Amendment to Table 3 7-4 '
prov ded that a revision to Table 3 7-4 is included with the next License Amendment request.
Hodifications to this column due to changes in high radiation areas may be made without prior na Liccuse Amendment provided that a revision to Table 3 7-4 is included with the next License Amendment) request.
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BASES 3/4.7.7 WASTE EFFLUENTS
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3/4.7.7.1 RADIOACTIVE SOLID WASTES Radioactive solid wastes are pemitted to be disposed of only at licensed offsite disposal areas.
3/4.7.7.2 RADIDACTIVE LIOUID WASTE Releases of radioactive materials in effluents will be kept at small fractions of the limits specified in 10 CFR'20 except under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in 10 CFR 20. The Licensee will exert his best efforts to keep levels of radioactive materials in effluents as low as reasonably achievable.
9 Radioactive liquid wastes are diluted in the plant discharge system prior to release up to a maximum dilution multiple of 7.24 x 10-6 minutes per gallon times the radioactive release rate in gallons per minute.
Radioactive liquid wastes are collected in tanks until h quantity
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sufficient for processing has accumulated. The processed liquids are directed to separate tanks where they are sampled and analyzed for radioactivity content prior to release. Discharges from the waste disposal system are m de through a recorder controller which provides a measure and control of the volume released. The volume released and the radioactivity analyses provides the basis for record keeping.
3/4.7.7.3 RADI0 ACTIVE GASEOUS WASTE Releases of radioactive materials in airborne waste will not exceed the concentration limits specified. The limit for iodine isotopes and particulate isotopes with half lives greater than 8 days was further reduced by a' factor of 700 to account for reconcentration in the food chain.
Gaseous wastes flow from the low pressure surge tank through the gas compressor (s) which discharge to the waste gas surge drum. The drum is pressurized and then allowed to decay before discharge to the primary i
vent stack. The gaseous discharge is. continuously monitored in the primary vent stack.
Coincident with the loss of exhaust fan suction, the vent line flow control valve will close, terminating the release.
i YANKEE-ROWE B 3/4 7-5 1
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PLANT SYSTEMS I
BASES 3/4.7.8 ENVIRONMENTAL MONITORING The operational environmental monitoring program is designed to demonstrate the adequacy of safeguards inherent in plant design and the ef fectiveness of established control measures for the releases of radioactive mat e rials.
Special attention is given to gamma spectrum analysis of samples in order
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to identify and reference nuclides presen't in plant ef fluents. Spec tra(of environmental samples are observed for the ingrowth of plant produced radionuclide s.
3/4.7.9 SNUB BERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maihtained during and following a seismic or other event initiating dynamic loads. Snubbers excluded f rom 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 ef fect on any safety-related system.
The visual inspcetion 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 found during,an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next in s pectio n.
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 ler.gthen the required inspection int erva l. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional' testing, that snubber may be exempted f rom being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or
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are similarly located or exposed to the same environ = ental conditions such as temperature, radiation, and vibration.
s Yankee Rowe B 3/4 7-6 Amendment No. JWI, 71
PLANT SYSTEMS 4-BASES When a snubber is found inoperable, an engineering evaluatio'n is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversly af fect'ed by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of -failure has imparted a significant effect or degradation on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the insta'lled snubbers will be functionally tested during plant shutdowns at 18 month inter'ials.
The service. life of a snubber is evaluated via manufacturer input and information through consideration of.the snubber service condit' ions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation 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 are not intended to affect plant operation.
Yankee Rowe B 3/4 7-6a Amendment No. 71 e
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ADMINISTRATTON CONTROLS g.
Records of training and qualification for current members of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
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Records 'of Quality Assurance activities required by the QA Manual.,
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Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PORC and the NSAR Committee.
1.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.
m.
Records of the service lives of all mechanical snubbers listed on Table 3.7-4 including the date at which the service life commences and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with requirements of 10 CFR Part 20 and shall be approved, maintained and.
adhered to for all operations involving personnel radiation exposures.
6.12 HIGH RADIATION AREA 6.12.1 Paragraph 20.203 " Caution signs, labels, signals, and controls." In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2), each high radiation area in which the intensity of radiation is 1000 mres/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Pe rmit.
- An individual or group of individuals permitted to enter such areas shall be provided with one or more.of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms uhen a preset integrated dose is received. Entry into such areas with this monitoring device may be made af ter the dose rate level in the area has been established and personnel have been made knowledgeable of them.
- Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection' duties,
. providing they are following plant radiation protectien procedures for entry into high radiation areas.
Yankee Rpwe 6-23 Amendment No. Jd', 71 Ord;;
det;d 0:::t:r 2',
1990
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