ML20037A459
| ML20037A459 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/14/1977 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19340A246 | List: |
| References | |
| NUDOCS 8001310534 | |
| Download: ML20037A459 (6) | |
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E]DDEANDUM FOR: Karl R. Coller, Assistaat Director for Operating l
Beactors,, DOR 1
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Darrell G. Eisenhet, Assistant Director for Operational i
Technology, DOR
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SUBJECT:
OCONEE, UNITS 1, 2 AND 3. TECHNICAL SPECIFICATIONS We have reviewed the November 30, 1976 letter by Duke Power Company j
which responds to your September 21, 1976 request that the teekicn1 specifications limit on the primary te secondary leek rate at the Oconae plants be changed from the present 10 spa to 1 gym. This response states that "there is no knom cor;alation between laakage rate and tube strength," and that "the limitation of 1 gym leakage through the steam generator tubes is considered to be overly con-
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- servative." Tha lie====e has met provided any basis:for.thess; state -- -- -
ments and, therafare, we find their response unacceptable.2Mu An analysia of a postulated control rod ejectinn accident with a primary to secondary leak of 10 gpa, as allowed by their present teeb ical speci-i fications, results in radiological consequenem which could exceed the 10 CFR Part 100 guidelines, as shown in Enclosure 1.
Because of this and in view of the recent ocmrences of sejor tube leaks at the Ocoeea planta (six laats in excess of 1 spa during'the last six months) we believe that the Standard Technie=1 Specification 3/4.4.'6.2 for BW reactors, limiting the primary to secondary leak rata to 1 gpc',, abould be imple==nted at the Oconee 1, 2 and 3 a-h=" power plants.
l While performing this review, we have also found tLat the Oconee P ants are operating without iodine coolant activity limita. In vice of the current tube failure problems at Ocones, we also believe it appropriate to apply coolant activity limits to assure that the radiolcoical conse-quences resulting from postulated design basis =eeldents are adequataly
===11 fractions of the 10 CFR Part 100 guidelin==. For this purpose we i
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Technical Specificatiov6s'for RW reactors (3/4.4.8 and 3/4.7.1.4) be implesenated for tha Oconee 1,'2 and 3 plants.
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Darrell G. Eisenhut, Assistant Director
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for Operational Technology
' '- Division of Operating Reactors
~Euclosurse: l 1.
Accideat Doses for the Oconee 1, 2 and 3 Plants and Assumptions i
- 2. ' Yropwed Technte=1 Specifications
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ENCLOSURE 1 1
TABLE 1 1
s ACCIDENT DOSES FOR THE OCONEE 1. 2 AND 3 PLANTS
- With Primary to Secondary With Primary to Secondary Leak of 10. gpm Leak of 1. gpm 2-Hour. Dose 2-Hour 2-Hour Dose 2-Hour to Thyroid Whole-Body to Thyroid Whole-Body (rem)
Dose (rem)
Dose (rem)
(rem)
6.3 0.3 5.8 0.2 Tube Failure Steam Generator Tube 83.
0.3 78.
0.2 Failure with a
_ Prior Iodine Spike W;,..J ac Main Steam Line
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13.
<0.1 1.3
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_i Failure Main Steam Line 35.
<0.1 3.6
<0.1 Failure with a Prior Iodine Spike Control Rod Ejection 400.
2.4 40.
0.2 Accident
- Assumes coolant activity limits as specified in the Standard Technical Sp'ecifications for B&W plants.
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TABLE 2
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STEAM GENERATOR TUBE FAILURE ACCIDENT - ASSUMPTIONS I
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Reactor Power = 2568 Mwth t
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Loss of condenser following the accident 3.
Primary coolant activity prior to the accident of 1. pCi/g of Dose Equivalent I-131 and 100/E pCi/g of noble gases
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Iodine spiking factor of 500 after the accident 5.
Failed steam generator isolated within 34 minutes following the accident 6.
89,000 lb. of.. primary coolant leak to the secondary side of the failed.
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Primary coolant activity prior to the accident for case with a concurrent iodine spike of 60. pCi/g of Dosn Equivalent I-131*
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8.
Secondary coolant activity prior to the accident of 0.1 pCi/g*
Dose Equivalent I-131 9.
Iodine decontamination faccor of 10 between water and steam 10.
Meteorological conditions corresponding to a 30-meter elevated release with fumigation and 1 m/see wind speed at a distance of 1609 meters (X/Q = 2.3x10 sec/m )
- As specified in the Standard Technical Specifications for BW reactors k
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TABLE 3 e
ASSUMPTIONS l
MAIN STEAM LINE FAILURE ACCIDENT 1.
Reactor Power = 2568 Mwth 2.
Primary coolant activity prior to the accident of 1. pCi/g of Dose Equivalent I-131 and 100/E pCi/g of noble gases
- 3.
Iodine spiking factor of 500 after the accident 4.
Primary coolant activity prior to the accidenc for case with a concurrent spike of 60. pCi/g of Dose Equivalent I-131*
5.
Secondary coolant activity prior to the accident of 0.1 pCi/g Dose Equivalent I-131*
Noadditionalfuelcladfailuresasaresultoftheaccben' t
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7.
Meteorological conditions corresponding to a 30-meter elevated release with fumigation and 1 m/sec wind speed at a distance of 1609 meters 0
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(X/Q = 2.3x10 sec/m )
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- As specified in the Standard Technical Specifications for B&W reactors f
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TABLE 4 ASSIBfPTIONS CONTROL ROD EJECTION ACCIDEhTS 1.
All releases through the secondary side safety and relief valves 2.
Reactor Power = 2568 Mwth I
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Loss of condenser following the accident t
4.
Primary coolant activity prior to the accident of 1. pCi/g of
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Dose Equivalent I-131 and 100[E pCi/g of noble gases
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28% of the fuel rods develop clad failures as a result of the accident 6.
10% of the core activity is In the gap
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100% of the gap activity in the damaged rods is released to the primary coolant at the time of the accident Secondary coolant activity prior to the accident of 0.1 pCi/g 8.
Dose Equivalent I-131*
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Iodine decontamination factor of 10 between water and steam
- 10. Meteorological conditions corresponding to a 30-meter elevated release with fumigation and 1 m/see wind speed at a distance of 1609 meters
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(X/Q = 2.3x10 sec/m )
- As specified in the Standard Technical Specifications for B&W plants I
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