ML15223A546
| ML15223A546 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/18/1980 |
| From: | Gammill W Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| Shared Package | |
| ML15223A547 | List: |
| References | |
| NUDOCS 8002080380 | |
| Download: ML15223A546 (6) | |
Text
DISTRIBUTION:
Dockets.cket File (3) 02
--NRC--PDR _4(3)-.
AR ~6 L PDR IE-5 ORB#4 Rdg JHeltemes-AEOD NRR Rdg Gray File +4 DEisenhut VNoonan Dockets Nos.
50-270 HDentoi--
STSGroup awd W-287 RVoj Imd r RCapra
-TJCarter CMiles-OPA WRussell RDiggs WGammill
.Biones (12)
Mr. William 0. Parker, Jr.
LShao BSdharf (10)
Vice President - Steam Product, on-JR11il1er
-'~TERA1-
- 3)
Duke Power Company NSIC (1)
P. 0. Box 2178 RReid 422 South Church Street.
.MFairtiTe Charlotte, forth Carolina 28242 ey RIngram Bear Mr. Parker:
By letter dated July 18, 1974 we initially Dequeted that Duke Power Company (DPC) submit-proposed Technical Specifictions (TS) tIhatoudestablish a program for steam generator tube inispection. -Sinice tha't -tme, a's 'outlined.
in the Background Section of the end i'sed Safety Evalualtion.,there have been e xtens ive co rres pondence and" staff disicussi ons ' between PC and NRC. res ulti ng in your submittal of Octoberjl6, 1979.
This'submittal contained a pro'posed amendment to* the Oconee tNuclcearstaion'(ON~s)" con' TS whichwould add a new TS 4.17, Steam Generator TuigSrellance. Susequentt, h October 16th submittal there have been discussions bet:Ween our staffs where vie indicated that the proposal was-.unacceptabl e,
."specifically inthe manner-proposed by DPC in Table 4.17-1 to take three sample inspections at the C-3 results level when the inspection results o6f t-he' s econd* sapile (C-2) - evel Indicate6 that more than 10% of the total tubes inspected, are d egrddtbso-oeta 1% of the Inspected tubes are'defectlye.- The NRC posi tion is.tat. if the C-2 results are as above, all tubes,_n,the afc ste enatr.
(SG) hib6 ID (ected.3)
We recognize that in the past DPC haqs perfon'ned an Initial sampling program Iexcess of the mini mum Standard TS fi -rst,sip
' an of3.,prS.I
- ddition, you have submitted your inspection. programs.in advance whenyrequested by our
~safand you have provided "tensi ye. afid'tm eslst us of yu pc tions.
The SG tubes are both the primary system and containment boundaries.
The tubes
'in certainb.f-the DNS SG haveaq pgt ~hs~y o xesie deradati on,, the rate of which has not been posiively established.
We recoqnpzeqhate.. past 18 months tube leakage incildis ti diminished.
However, because of the potential adverse, effects on public health and safety.
which could result from an acc dent whi le operating ith4a ignifint number of SG tubes either leaking or susceptible to accident-induced leakage, we believe that appropriate changes to TS are needed to.assure a high degrge pf Sd tube integrity. The basis for this, Ipos Ition Is iiprovidIe'd In our Safety Evaluation, copy of which is enclosed. Accordigy r~a~ nnn usw
Mr. William 0. Parker, Jr.
twenty (20) days of the date of this letter or five (5) days before startup of OConee, Unit No.
whichever occurs first, f you do not agree with this course of action, includingyour, reasons.
Sincerely, W.
mm Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors
Enclosures:
- 1.
Proposed TS
- 2. Safety Evaluation cc w/enclosures:
See next page
- See previous yellow for concurrences C-EB:DOR STS Group:DOR VNoonan*
DBrinkman*
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-n - -----
DATE
/.580 80 1//s0o80 NRC FORM 318 (9-76) NRCM 0240
- U.S.
GOVERNMENT PRINTING OFFICE-1979-289-369
Mr. Robert Hi Groce
-2 not agree with this course of action, i t'nag your reasons, we plan to initiate steps to-issue the enclosed f OS..
Sincerely, W. P. Gammill, Acting Assistant Director for Operating Reactor Pro cts,"
Division-of Operating Reactors
Enclosures:
- 1.
Proposed TS
- 2.
Safety Evaluation cc w/enclosures:
See next page C-EB
~
STS rouW VNoonan 11/680 1/1580 OFF.CE ORB#4:DOR ORB#4:DOR ORB#4:DOR C-ORB#4:DOR A-AD-ORP:DOR OELD SURNAMEp R.ngram Sokey/c
.Mairt-ile RRei-d....
WGammill 1/1-/80 1/ /80 1//80 1/ /801/
80//0 DATE8 I
NRC FORM 318 (9-76) NRCM 0240
- U.S.
GOVERNMENT PRINTING OFFICE: 1979-289-369
Mr. William 0. Parker, Jr.
-2 twenty (20) days of the date of this letter or five (5) days before startup of Oconee, Unit No. 1, whichever occurs first, if you do not agree with this course of action, including your reasons.
Sincerely, W. P. Gammill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors
Enclosures:
- 1. Proposed TS
- 2. Safety Evaluation cc w/enclosures:
See next page
o'f
-UNfED STATES o0 NUCLEAR REGULATORY COMMISSION X
WASHINGTON, D. C. 20555.
January 18, 1980 Dockets Nos. 50-269, 50-270 and 50-287 Mr. William 0. Parker, Jr.
Vice President - Steam Production Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
By letter dated July 18, 1974 we initially requested that Duke Power Company (DPC) submit proposed Technical Specifications (TS) that would establish a program for steam generator tube inspection. Since that time, as outlined in the Background Section of the enclosed Safety Evaluation, there have been extensive correspondence and staff discussions between DPC and NRC resulting in your submittal of October 16, 1979. This submittal contained a proposed amendment to the Oconee Nuclear Station (ONS) common TS which would add a new TS 4.17, Steam Generator Tubing Surveillance. Subsequent to the October 16th submittal there have been discussions between our staffs where we indicated that the proposal was unacceptable, specifically in the manner proposed by DPC in Table 4.17-1 to take three sample inspections at the C-3 results level when the inspection results of the second sample (C-2) level indicate that more than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective. The NRC position is that if the C-2 results are as above, all tubes in the affected steam generator (SG) should be inspected.
We recognize that in the past DPC has performed an initial sampling program in.excess of the minimum Standard TS first sample of 3% per SG. In addition, you have submitted your inspection programs in advance when requested by our staff and you have provided extensive and timely results to us of your inspec tions.
The SG tubes are both the primary system and containment boundaries. The tubes in certain of the ONS SG have a past history of excessive degradation, the rate of which has not been positively established. We recognize that in the past 18 months tube leakage incidents have diminished.
However, because of the potential adverse effects on public health and safety which could result from an accident while operating with a significant number of SG tubes either leaking or susceptible to accident-induced leakage, we believe that appropriate changes to TS are needed to assure a high degree of SG tube integrity. The basis for this position is provided in our Safety Evaluation, a copy of.which is enclosed. Accordingly, please inform us in writing within
Duke Power Company cc w/'.nclosure(s):
Mr.
lliam L. Porter Mr. Robert B. Borsum Duke Power Company Babcock & Wilcox Post Office Box 2178 422o t Offi c Box 217 Nuclear Power Generation Division 422 outhChurh SteetSuite 420, 7735 Old Georgetown Road Charlotte, North Carolina 28242 Bethesda, Maryland 20014 J. Michael McGarry, III, Esquire Manager, LIS DeBevoise & Liberman NUS Corporation 700 Shoreham Building 2536 Countryside Boulevard 806 15th Street, N.W.
Clearwater, Florida 33515 Washington, D. C.
20005 cc w/enclosure(s) and incoming Oconee Public Library dtd.
10/16/79 201 South Spring Street Walhalla, South Carolina 29691 Office of Intergovernmental Relations 116 West Jones Street Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region IV Office ATTN:
EIS COORDINATOR 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Francis Jape U. S. Nuclear Regulatory Commission P. 0. Box 7 Seneca, South Carolina 29678