ML19209C990
| ML19209C990 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/02/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19209C991 | List: |
| References | |
| NUDOCS 7910180556 | |
| Download: ML19209C990 (11) | |
Text
.
[$
UNITED STATES t
NUCLEAR REGULATORY CCMMisslON i IM.$
WASHINGTON, D. C. 20585
'+
o' THE TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING CCMPANY 00CKET NO. 50-346 DAVIS-BE5SE NUCLEAR POWER STATION, UNIT NO. 1 MENCMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License 'to. NPFv3 1.
The Nuclear Regulatory Comission (the Cocmission) has found that:
A.
The application for amendment by The Toledo Edison Company and The Cleveland Electric Illuminating Comoany (the licensees) dated July 27, 1979, as supplemented August 17, 1979, 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 facilf ty will operate in confamity with the application, the provisions of the Act, and the rules and regulations of the Ccumission; C.
'here is reasonable assurance (1) that the actf vities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in ecmpliance with the Camissten's regulaticns; D.
The issuance of this amendment will not be inimical to the coatoon defense and security ci 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 app 11 cable requirements have been satisfied.
1177 254 7910180
2-2.
Accordingly, the license is amended by changes to the Technical Specificatiens as indicated in the attachment to this license amen # ment, and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follcws:
(2)
Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. ?!, are hereby incorporated in the license.
Toledo Edisen Company shall operate the facility in accordance wich the
.echnical Specificaticns.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CCMMISSI0ft l
^ h. 's %
%nobert W. Reid, Chief Operating Reactors Branch #4 Division of Operating React:rs
Attachment:
Changes to the Technical Spacifications Ca:e of ssuance: October 2, 1979 O
1177
)SS t
ATTACHMENT TO LICENSE AMENDMENT NO. 21 FACILITY *CPERATING LICENSE NO. NPF-3 DOCKET N0. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enc"osed pages as indicated.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf p6ges a e also provided to maintain document ccmpleteness.
Paces 3/4 4-6 3/4 4-7 3/4 4-8 3/4 4-9 3/4 4-10 3/4 4-12 1177 156 i
REArTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with:
a.
A steam bubble, b.
A water level between 45 and 305 inches.
APPLICABILITY: MODES 1 and 2.
ACTION:
With the pressurizer inoperable, be in at least HOT STANDBY with the control rod drive trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ddRVEILLANCE REQUIREMENTS 4.4.4 The pressurizer shall be demonstrated OPERABLE by verifying pressurizer level to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1177
]57 D VIS-SESSE, UNIT 1 3/4 J-5
REACTOR COOLANT SYSTEM STEAM GENERATORS l
LIMITING CONDITION FOR OP'ERATION 3.4.5 Each steam generator shall be OPERABLE with a water level between 18 and 348 inches.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
a.
With one or more steam generators inoperable due to steam generator tube imperfections, restore the inoperable generator (.s) to OPERABLE status prior to increasing 7,yg above 200'F.
b.
With one or more steam generators inoperable due to the water level being outside the limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREuENT3 4.d.5.0 Each steam generator shall be demonstrated OPERABLE by perfomance of the following aucmented inservice inspection program and the recuirements of Scecification 4.0.5.
4.4.5.1.
Steam Generator Samole Selection and Inscection - Each steam generator shall be cetemined OPERABLE curing shutdown oy selecting and insoecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generacce Tube Samole Selection and Inscection - The : team generator tuce minimum sample size, inspection result classification, and the corresponding action recuired shall be as specified in Table 4.a-2.
The inservice inseection of steam generator tubes shall be performed at the frecuencies scecified in Specification 4.4.5.3 and the ins:ected tubes shall be verified acceptable :er the acceptance criteria of Specification 4.4.5.4 The tubes selected for each inservice inspection shall include at least 3%
of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
a.
The first samole inspection during each inservica 'nscection (subsecuent to the baseline inscection) of each steam generator shall include:
1.
All nonclugged tubes that previously had detectable wall cenetrations (> 20%).
p 2.
At least 50% of the tubes inspected shall be in those
}
areas where exoerience has indicated potential problems.
0 AVIS-BESSE, UNIT 1 3/4 4-6 Amencment No. 21 1177 J58
REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued)
J.
A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a e
full tube inspection.
b.
Tubes in the follcwing groups may be excluded frcm the first randcm samcle if all tubes in a group in both steam generators are inspected.
No credit will be taken for these tubes in meeting minimum sample size requirements.
1.
Group A-1: Tubes within one, two or three rows of the open inspection lane.
2.
Group A-2:
Tubes having a drilled opening in the 15th support plate.
c.
The tubes selected as the second and third samples (if recuired by Table 4.4-2) during each inservice insLection may be subjected to less than a full tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were creviously found.
2.
The inspections include those portions of the tubes where imperfections were previcusly found.
The results of each sample inspection shall be classified into one of the folicwing three categories:
Catecory Inscecticn Results C-1 Less than 5% of the total tJbes inspected are degraded tubes and ncne of the inspected tubes are defective.
C-2 One or mere tubes, but not more than 15 of the total tubes inspected are defective, or between 55 and 104 of :ne total tubes ir.spected are degraded tubes.
C-3 More than 105 of the total tubes inspected arc degraded tubes cr more than 1" of the inscected tubes are defective.
H77 JS9 iUAVIS-3 ESSE, UNIT 1 3/4 4-7 Amen:: ment Nc. 21
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
Notes:
(1)
In all inspections, previously degraded tubes must exhibit significant (> 10%) further wall penetrations to be included in the above per-centage calculations.
(2) Where special inspections are performed pursuant to 4.4.5.2.b, defective or degraded tubes found as a result of the inspection shall be included in determining the Inspection Results Category for that special inspection but need not be included in determining the Inspection Results Category for the general steam generator inspection.
4.4.5.3 Insaection Frecuencies - The above required inservice inspections of steam generator tubes snall be performed at the following fraquencies:
a.
The baseline inspection shall be performed to coincide with the first scheduled refueling outage but no later than Acril 30, 1980.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If the results of two consecutive inspections for a given group
- of tubes following service under all volatile treatment (AVT) conditions fall into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval for that group may be extended to a maximum of 40 months.
b.
If the results of the inservice inspection of a steam generator performed in accordance with Table 4.4-2 at 40 month intervals for a given group
- of tubes fall in Category C-3, subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previous inspection.
The increase in inspection frecuency shall apply until a subsequent inspection meets the conditions specified in 4.4.5.3a and the interval can be extended to 40 months.
c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inscection scecified in Table 4.4-2 during the shutdown subsecuent to any of the folicwing conditiens.
1.
Primary-to-secondary tube leaks (not including leaks originating frem tube-to tube sheet welds) in excess of the limits of Specification 3.4.5.2.
'A group of tuces means:
i (a) All tubes inspected pursuant to 4.4.5.2.b, or (b) All tutes in a steam generator less those inspected pursuant to 4.4.5.2.b.
0 AVIS-BESSE, UNIT 1 3/4 4-8 Amendment No. 2*.
s r
t i177 J60
REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued) 4 I
2.
A seismic occurrence greater than the Operating Basis Earthquake.
3, A loss-of-coolant accident requiring actuation of the engineered safeguards.
4 A main steam line or feedwater line break.
d.
The provisions of Specifica; ion 4.0.2 are not applicable.
4.4.5.4 Acceptance Criteria a.
As used in this Specification:
1.
Imoerfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the ncminal tube wall thickness, if detectable, may be considered as imperfections.
2.
Cecradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
3.
Decraded Tub. means a tube containing imperfections > 20%
of the nominal wall thickness caused by degradation.
4 i Decradation means the percenta.! of the tube wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the plugging limit.
A tube containing a defect is defective.
6.
Pluccina Limit means the imperfection depth at or beycnd wnicn the tuoe shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube wall thickness.
7.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Eartncuake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, a:ove.
I S.
Tube Inscection means an inspection of the steam generatcr tute from the point of entry ccepletely to the point of exi*
i CAVIS-BESSE, UNIT 1 3/4 4-9 Amendment No. -I 1177
.161
REACTOR CCOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued) 9.
Preserive Inscection means an inspection of the full lengtn of eacn tuce in each steam generator oerfarned by eddy current technicues prior to service to establish a baseline condition of the tubing.
This inspection shall be performed prior to initial POWER OPERATION using the ecuipment and techniques expected to be used during subsequent inservice inspections.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2 4.4.5.5 Recorts Following each inservice inspection of steam generator tubes, a.
the number of tubes plugged in each steam generator shall be reported to the Comission within 15 days.
b.
The complete results of the steam generator tube inser/ ice inspection shall be submitted on an annual basis in a report for the period in wnich this inspection was comoleted. This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged.
Results of steam generator tube ins::ections which fall inte c.
Category C-3 and recuire prcmpt notification of the Cocinission shall be reported pursuant to Specification S.9.1 prior to resumotion of plant operation. The written followup of this re:: ort shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
1.2.5.5 The steam generator shall be demcestrated CPERABLE by verifying steam generator level to ::e within limits at least once aer 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1177 362 r
CAV!S-3 ESSE, UNIT 1 3/2 2-10
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TABLE 4.4-2 SIEAM GLNEllATOH TuuE INSPECTIONI2) ab ISI SAMPt E INSPECTION 2ND SAMPLE INSPECTION 3flD SAMPLE INSPECilON n
in Sample Sise licusit As.tuun llcquised flesult Actu>si lleisuued fleusle Acepsi llequued a
oi
[]
A snininuuri of C-I None N/A N/A N/A N/A
(
C -2 Plug defective toises C-l None N/A N/A Q
4:ul ing:es.: aikhtunnal Plug defective tulses C -l None
~
2S suises in sliis S. G-C-2 arul isig>cci ail
- tuinal C-2 Plug e8.:lective tut.es 4S tulses in teus S. G.
pg,,,,,,;,,n,o, C-3 C-3 result of fisse sample Peeform union los C-3 C-3 sesult of lust N/A N/A sample C-3 Inspect all tulies in All ollies M
this S. G., plug de S G s ase N""'
N/A
'N/A 8-lective toises asul C-1 j-inspect 2S tulses iss Some S. G.s each other S. G-Peslosen action for N/A N/A C-2 imt su)
C-2 sesult of secomi editatsosial 5,anple Prosopt notifica: ion S. G. are to NitC pinusant C-3 to specificatios Aikhtional ingiect all tulses in 6 9.1 S G is C-3 eacle S. G. ami plug defective tubes.
Prosnpt notelication N/A N/A to NflC pususant to specification g.
G 9.1 a
~
R S - 3 "s ""lusing an suspection
'""98""*""a"""i'**'"h'"""'"'""**"""'"**d
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<+
v (2) For tut >ea inspected pursuant to 4.4.5.2.is.
No action la resluired for C-1 results. For f
C-2 results in one or looth stearn generators. plug <~afective tubes.
For C 3 results in one A
or both ateam generators, plug defective tutea and provide prompt notification of HRC pursuant to Specification 6.6, 6