ML20210S051
| ML20210S051 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/24/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20210S057 | List: |
| References | |
| TAC 65069, NPF-03-A-094 NUDOCS 8605200419 | |
| Download: ML20210S051 (15) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3
WASHINGTON, D. C. 20555
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TOLED0 EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The application for amendment by the Toledo Edison Company)and A.
The Cleveland Electric Illuminating Company (the licensees dated September 1, 1983, as revised January 30, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
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. NPF-3 is hereby amended to read as follows:
8605200419 860424 PDR ADOCK 05000346 P
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 94, are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REG ATORY COMMISSION I.
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oh FF. Stolz, Directo PWR Project Directora e #6 0 ision of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 24,1986 h
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ATTACHMENT TO LICENSE AMEN 0 MENT N0. 94 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET N0. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 7-20 3/4 7-20 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 3/4 7-24 3/4 7-24 3/4 7-25 thru 3/4 7-36 3/4 7-36 l
B 3/4 7-5 B 3/4 7-5 B 3/4 7-Sa 6-19a 6-19a
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PLANT SYSTEMS 4
SURVEILLANCE REQUIREMENTS (Continued) 4 3.
Verify that the make up flow of the system is 300 cfm i 10% when supplying the control room with outside air.
f.
After each complete or partial replacement of a HEPA filter bank by verifying-that the HEPA filter banks remove > 99% of the D0P when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 3300 cfm + 10%.
9 After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove
> 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 3300 cfm_110%.
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DAVIS-BESSE, UNIT 1 3/4 7-19 L -.
PLANT SYSTEMS 3/4.7.7 SNUBBERS LIMITING CONDITION FOR OPEBATION 3.7.7 All safety related snubbers shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
(MODES 5 and 6 for sn'ubbers located on systems required OPERABLE in those MODES).
CTION:
With one or more snubbers inoperable:
1.
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> a.
replace or restore the inoperable snubber (s) to OPERABLE status, or 2. verify system operability with the snubber (s) inoperable by engineering evaluation within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or
- 3. declare the supported subsystem inoperable and follow the appropriate ACTION statement for that system.
and, for snubbers which have failed either the visual or functional test:
b.
Perform an engineering evaluation within 90 days to deter-mine if any safety-related system or component has been adversely affected by the inoperability of the snubber and if the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.1 The provisions of Technical Specification 3.0.4 are not applicable for the component or system.
SURVEILLANCE Pr0UIREMrNTS 4.7.7 Each snubber 2 shall be demonstrated OPERABLE by the requirements of the following surveillance programs and pursuant to require-ments of Specification 4.0.5.
4.7.7.1 Visual Inspection Program 1Engineering evaluation is not required when a snubber is removed for surveillance testing provided it' is returned to OPERABLE status within the requirements of action statement a.
2Safety related snubbers are listed in the latest revision of applicable surveillance test procedure (s). Snubbers may be added to, or removed from, safety-related systems and their assigned groups without prior Licensing Amendment.
DAVIS-BESSE, UNIT 1 3/4 7-20 Amendment No. 94 I
PLANT SYSTEMS SURVEILLANCE REOUIREE hIS (Continued) a.
General Requirements At least once per inspection interval, each group of snubbers in use in the Plant shall be visually inspected in accordance with Specification 4.7,.7.1.b and 4.7.7.1.c.
Visual inspections may be performed with binoculars, or other visual support devices, for those snubbers that are difficult to access and where required to ke'ep exposure as low'as reasonably achievable. Response to frilures shall be in accordance with Specification 4.7.7.1.d.
b.
Inspection Interval and Sample Criteria The inspection interval and sample criteria may be applied on the basis of snubber groups. The snubber groups may be established based on physical characteristics and accessi-bility. Inaccessible snubbers are defined as those locat-ed: (a) inside containment, (b) in high radiation exposure zones, or (c) in areas where accessibility is limited by physical constraints such as the need for scaffolding.
Visual inspections for a group shall be performed in accordance with the following schedule:
Snubbers are divided into four (4) groups: " Accessible" -
Group I and " Inaccessible" - Group II for either hydraulic or mechanical.
No. of Inoperable Snubbers Within a Group -
Subsequent
- Group Visual Per Inspection Interval Inspection Interval 3, 4,
5 0
18 months 1
12 months 2
6 months 3, 4 124 days 5,6,7 62 days 8 or more 31 days The inspections for a group shall include 100 percent of snubbers in that group.
3The inspection interval shall not be lengthened more than one step at a time, and 4The provisione of Specification 4.0.2 are not applicable.
5All the time intervals are +25%, except that the inspection of inaccessible snubbers may be deferred to the next shutdown when plant conditions allow 5 days for inspection.
DAVIS-BESSE, UNIT 1 3/4 7-21 Amendment No. 94 L
PI.AhT SYSTEMS SUILVEIIlMCL REOUIRPMENTS (continued) c.
Acceptance Criteria A snubber shall be considered OPERABLE as a result of a visual inspection if:
(1) there are no visible indications of demage or inoperability, and (2) attachments to the foundation or supporting structure are secure.
d.
Response to Failures For each snubber unit which does not meet the visual inspection acceptance criteria of Specification 4.7.7.1.c:
Determine the snubber OPERABLE by functionally testing the snubber per Specification 4.7.7.2, unless the (hydraulic) snubber was determined inoperable because the fluid port was found uncovered; pR 1.
Perform the ACTION specified in 3.7.7a; and 2.
Perform an engineering evaluation as specified in 3.7.7.b.;
and 3.
Increase the frequency of group inspection as de-scribed in Specification 4.7.7.1.b, unless the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible.
4.7.7.2 Functional Test Program a.
General Requirements At least once per inspection interval a representative sample of each group of snubber in use in the Plant shall be functionally tested in accordance with Specifications 4.7.7.2.b and 4.7.7.2.c.
Response to the failures shall be in accordance with Specification 4.7.7.2.d.
For all snubbers, functional testing shall consist of either bench testing or inplace testing.
b.
Inspection Interval and Sample Criteria The snubbers may be categorized into groups based on physical characteristics. Snubbers are divided into four (4) groups: " Accessible" - Group 1 and " Inaccessible" -
Group II for either hydraulic or mechanical. Each group may be tested independently from the standpoint of per-forming additional tests if failures are discovered.
DAVIS-BESSE, UNIT 1 3/4 7-22 Amendment No. 97,94
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PLWT SYSTEMS e
SURVEILUNCE REOUIRrMENTS (Continued)
The inspection interval for functional testing shall be 18 months.
Snubbers which are scheduled for removal for seat mainte-nance may be included in the test. sample prior to any maintenance on the snubber.
A The representative sample shall consist of a't least 10 percent (rounded off to next highest integer) of each group of snubbers in use in the Plant. The selection process shall l
ensure that all snubbers, regardless of their accessibili-8 ty classification, are functionally tested at least once every ten inspection intervals.
c.
Acceptance Criteria j
'j For hydraulic snubbers (either inplace testing or bench testing), the test shall verify that:
1.
Snubber piston will allow the hydraulic fluid to
" bypass" from one side of the piston to the other to assure unrestrained action is achieved within the specified range of velocity or acceleration in both
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tension and compression.
2.
When the snubber is subjected to a movement which creates a load condition that exceeds the specified range of velocity or acceleration, the hydraulic fluid is trapped in one end of the snubber causing suppres-sion of that movement.
I 3.
Snubber release rate or bleed rate, where required, occurs in compression and tension.
For mechanical snubber in place and bench testing, the test shall verify that:
1.
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified naximum drag force.
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Activation (restraining action) is achieved in both j
tension and compression.
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f Permanent.or other exemptions from functional testing for individual I
6 snubbers in these categories may be granted by the Commission only if l
a justifiable basis for exemption is presented.
DAVIS-BESSE, UNIT 1 3/4 7-23
PLANT SYSTEMS, SURVEILLANCE _REOUIREMINTS (Continued) d.
Response to Failures For each inoperable snubber per Specification 4.7.7.2.c:
1.
Perform the ACTIONS specified in 3.7.7a and 3.7.7b; and 2.
Within the specified inspection interval, functionally test an additional sample of at least 10 percent of the snubber units from the group that the inoperable snubber unit is in.
The functional testing of an additional sample of at least 10 percent from the inoperable snubber's group is required for each snubber unit determined to be inoperable in subsequent functional tests, or until all snubbers in that group have been tested; and 3.
The cause of snubber failure will be evaluated and, if caused by a manufacturing or design deficiency, all snubbers of the same or similar design subject to the same defect shall be functionally tested within 90 days from determining snubber inoperability. This testing requirement shall be independent of the requirements,in 4.7.7.2.d(2) above.
DAVIS-BESSE, UNIT 1 3/4 7-24 Amendment No. 75,94 (Tables 3.7-3 and 4.7-4 deleted.
Next page is 3/4 7-36).
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PLANT SYSTEMS 3/4.7.8 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.8.1 Each sealed source containing radioactive material either in
, excess of 100 microcuries of beta and/or gama emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 micro-
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curies of removable contamination.
APPLICABILITY: At all times.
ACTION:
Each sealed source with removable contamination in excess of
- a.
the above limit shall be immediately withdrawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Comission Regulations.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.8.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
4.7.8.1.2 Test Frequencies - Each category of sealed sources shall be tested at the ft:quency described below, a.
Sources in use (excluding startup sources and fission detec-tors previously subjected to core flux) - At least once per six months for all sealed sources containing radioactive material:
DAVIS-B'iSSE, UNIT 1 3/4 7-36 Amendment No. 94 (Tables 3.7-3 and 4.7-4 deleted.
Previous page is 3/4 7-24).
PLANT SYSTEMS BASES PLANT SYSTEMS 3/4[7.7 SNUBBERS BASES f
All safety-related snubbers are required OPERABLE to ensure that the structural. integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic event.
Snubbers excluded frcm this inspection program are those installed on safety-related systems for loads other than seismic or 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 during a seismic event.
Inoperable is defined as:
1.
For visual test The fluid no lon'er is supplied to the valve block, or a.
g b.
Mounting pins are disengaged from the snubber.
c.
Attachment to foundation or supporting structure is not secure.
2.
For functional test The snubber (excluding end anchors, i.e., pin-to pin) does not a.
meet specified test criteria.
The 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 found during an inspec-tion. 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 257.) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
Mien the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generi-cally susceptible, and verified by functional testing, that snubber may be exempted from 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 are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
DAVIS-BESSE, UNIT 1 B 3/4 7-5*
Amendment No. 94
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PLANT SYSTEMS BASES When a snubber is found inoperable through a visual or functional test, an
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engineering evaluation is performe.d, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of
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the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degrada-g tion on the supported, component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be Oractionally tested at 18-month intervals. Observed failures of these sample snubbers shall require functional testing of additional units. When a snubber is found to be inoperable due to failure to lock up or failure to move (i.e., frozen in place), the cause will be evaluated for further action or testing.
In cases where the cause of failure has been identified, additional snubbers that have a high probability for the same type of failure or are being used in the same application that caused the failure shall be tested. This requirement increases the probability of locating inoperable snubbers without testing 100% of the snubbers.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
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DAVIS-BESSE, UNIT I B 3/4 7-Sa:
lbnendment No. 94 e
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i PLANT SYSTEMS BASES 3/4.7.8 SEALED SOURCE CONTAIMINATION The limitations on removable contamination for sources requirin leak testing, including alpha enitters, is based on 10 CFR 70.39(c) g limits for plutonium. This limitation will ensure that leakage from by product, source, and special nuclear material sources will not exceed a
allowable intake values.
3/4.7.9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinquish fires occ'uring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or snrinklers, and fire hose stations. The collective 4
capability of the fire suppression systems is adequate to minimize i
potential damage to safety related equipment and is a major element in the facility fire protection program.
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In the event that portions of the fire suppression systems are i
inoperable, alternate backup fire fig'hting equipment is required to be
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made available in the affected areas until the inoperable equipment is restored to service.
In the event th5 fire suppression water system becomes inoperable, 3
immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evalua-tion of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
3/4.7.10 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures i
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that fires will be confined or adequat'ely retarded from spreading to j
i adjacent portions of the facility..
This design feature minimizes the possibility of a single fire rapidly involving several areas of the j
facility prior to detection and extinguishment. The penetration fire l-barriers are a passive element in the facility fire protection program and are subject to periodic incpections.
Ouring periods of time when the barriers are not functional, a cen-tinuous fire watch is required to De maintained in the vicinity of the i
affected barrier until the barrier is restored to functional status.
DAVIS-GESSE, UNIT I B 3/4 7-6 Amendment No. 9-
ADMINISTRATIVE CONTROLS f
e Records of changes made to Optrating Procedures.
e.
f.
Records of radioactive shipments.
Records of sealed source and fission detector leak tests g.
and results.
h.
Records of annual physical i'nventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
Records and drawing changes reflecting facility design modifi-a.
cations made to systems and equipment described in the Final Safety Analysis Report, b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
Records of radiation exposure for all individuals entering c.
radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
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Records of transient of operational cycles for those facility e.
co=ponents identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
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.
i.
Records of Quality Assurance activities required by the QA Manual.
J.
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 reetings of the SRS and the CfjR3.
1.
Records for Environrental Qualification which are covered under the provisions of paragraph 6.13.
i DAVIS-BESSE, UNIT 1 6-19 Amendment No. 5, Order'dtd. Oct.
,1980 s
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ADMINISTRATIVE CONTROLS RECORD RETERTION (continued)
Records of analyses required by the radiological environmental m.
monitoring program that would permit evaluation of the accuracy of the analyses at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.
,o.
Records of the service lives of all safety related hydrau-f lic and mechanical snubbers including the date at which the. j service life cocmences and associated installation and
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, maintenance records.
s.
s DAVIS-EESSE, UNIT 1 6-19a, Amendment No. gy,94
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