ML20031C822
| ML20031C822 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/22/1981 |
| From: | Rooney V Office of Nuclear Reactor Regulation |
| To: | Rich Smith VERMONT YANKEE NUCLEAR POWER CORP. |
| References | |
| TASK-2.F.1, TASK-TM NUDOCS 8110080622 | |
| Download: ML20031C822 (6) | |
Text
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(4 SEP2 9, aC Docket No. 50-271 f)
SEP 2 2 1981 w
Mr. Robert L. Smith 4
Licensing Engineer Vemont Yankee Nuclear Power Corporation 1671 Worcester Road Framingham, Massachusetts 01701
Dear Mr. Smith:
By letter dated Jarnary 13, 1981 you took exception to Post-THI Action Plan requirement II.F.1 which we sent to you by letter dated October 31, 1980.
In the enclosure to this letter we have commented on the exceptions you have taken : id your justification for these erceptions.
We discussed our comments with members of your staff on September 17,1981, and we understand that you are in the process of taking into account these considerations. Please infom us of your resolution of these comments within 30 days of your receipt of this letter.
Sincerely, ORIGINAL SIGEED BY Vernon L. Rooney, Project Manager Operating Reactors Branch f2 Division of Licensing
Enclosure:
Staff Responses to Vermont Yankee Deviations en D
RIBUTION:
on Action Plan Item II.F.1 ocket F?le E. Conner NRC PDR cc: w/ enclosure Local PDR See next page ORB #2 Rdg.
D. Eisenhut CILD IE(3)
V. Rooney S. Norris NSIC TERA ACriS (10)
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Mr. Robert L. Smith cc:
'Mr. W. F. Conway John R. Stanton, Director President.& Chief Operating Officer Radiation Control Agency Vermont Yankee Nuclear Power Corp.
Hazen Drive 411 Western Avenue Concord, New Hampshire 03301 Orawer 2 West Brattleboro, Vermont 05301 John W. Stevens Conservation Society of
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Southern Vemont Mr. Louis H. Heider, V.P.
P. O. Box 255 Yement Yankee Nuclear Power
- Townshend, Yemont 05353 Corocration Rayrond H. FcCandles's
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P5 Research Dn,ve
. Radiation Control Prohgicn1 H1th ram Westboro, Massachusetts 01581 0ccupational & Radiol Administration Building John A. Ritscher, Escuire Mantpelier, Venent 05502 Ropes & Gray 226 Franklin Street Ned England Coalition on Nuclear Boston.. Massachusetts 02110 Pollution Hill and Dale Fam Laurie Burt West Hill - Faraway Road Assistant Attorney General Putney, Vermont 05346 5nvironmental Protection Division n2 Attorney General's Office.
Public Service Board One Ashburton Place,19th Floor State of Yement Boston, Massachusetts 0210E 120 State Street Montpelier, Yemont 05502 Ronald J. Wilson 81018th' Street, N. W.
W. P. Murohy, Plant Superintendent Suite 802 Vermont Yankee Nuclear Power Washington, D. C.
20005 Corporation P. O. Box 157 Honorable M. Jerome Diamond Vernon, Ver nont 05354 Attorney General State of Vermont David White 109 State Street Co-Director Pavilion Office Building Vemont'Public Interest Montpelier, Vermont 05502 Reserach Group, Inc.
43 State Street Vermont Yankee Oecomissioning Montpelier, Vertnont 05502 Alliance 127 Main Street Vemont Yankee Decomissioning l
3rattleboro, Vermont. 05301 Alliance l
5 State Street Mr. E. W. Jackson Box 1117 Manager of Operations Montpelier, Yemont 05502 t
l Vermont Yankee Nuclear Power Corp.
411 Western Avenue Brooks Memorial Library Drawer 2 224 Main Street l
West Brattleboro, Vermont 05301 Brattleboro, Verrent 05301 W
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Mr. ' Robert L. Smith cc:
Resident Inspector c/o U. S. NRC P. O. Box 176 Vernon, Vemont 05453 O
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a-Staff Responses to Vermont Yankee VERMONT YANKEE Deviations on Action Plan Letter: '01/13/81 Item II.F.1 DEVIATION Proposes to use instrument reading-out in terms of mR/hr and tr
_ procedure to convert reading to either Xe-133 equivalent or actual noble gas concentra-tion.
POSITION Acceptable, subject to preparation of suitable procedure for such conversion.
-DEVIATION 2
Takes exception to using value of 10 uti/cc for sampling and analysis of.
radiciod'ines and particulates in plant effluents.
Doesn't enme out and say they won't mee,t the requirement but gives four justifications, noted and
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cermented-on as folic.cs:
(1)
States intep cted activ.ity on sampler redia would be 85 Ci of I-131 plus other noble gases for '.'ermont Yankee and up to 425 Ci of I-131 at l'aine Yankee.
Plant personnel would not be allowed to handle a sample of such high activity.
2 Cc: ent:
Per Tcble 11.F.1-2, activity is stated to be 10 uti/cc but not specifically 1-131; licensee's figure of 85 Ci probably correct but should assume only 0.5 MeV.
Because of some conservatism in these numbers for most accidents, it's not necessary to add-in noble gases when calculating shielding and doses.
Using silver zeolite as a radiciodine adsorber
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VERMONT YANKEE i.
would minimize retention of noble gases.
Shielding, remote handling tools, shielded transport devices, plus training l
should be employed to enable plant personnel to handle samples (no one said it was going to be easy).
(2)
States concentration could only be produced At stack by purging contain-
. ment fuel-melt.LOCA to stack unfiltered.
All other sources would be 2
decades lower than 10 uCi /cc.
Comment:
Our calculation for a fuel melt LOCA as described would be 0
10 uti/cc, which agrees with A!JSI N320-1979.
Bf;WL-1635 3
2 recommends a value of 10 - uCi/cc. The value of 10 uCi/cc 2
already contains a factor of 10 credit for filtration, less than TID release, and containment plate-out.
(3)
In the event of halogen r elease, licensee states there exists more reli-able and r easonable methods for a quantitative assessment of the release and gives the examples of direct measurecerit of the source and offsite sampling for 1-131.
Ccmment:
Direct reasur ement under accident circumstances, where gamma i
radiation levels frcm ncble cas releases are from 3 to 6 orders
),
of magnitude higher than iodine, are considered by the staff to be impracticable with state-of-the-art equipment.
Offsite
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sampiing, with delays in sample procurement and analysis, is not a viable alternative for the immediate need dictated by l
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L VEPJ40NT YANKEE 3-emergency planning considerations. The need is for quantita-tive evaluation cf releases in tems of minutes, not dr s.
(4)
Licensee references EPRI presentation to Commission on 11/18/0 as justi-fication for assuming los releases of halogens (Stratton-Malinauskas work ).
. Comment:
A draf t NRC report submitted to the Commission indi' cates that-suffi'cient evidence has not been produced to justify lowering relese rates for accident dose / design calculations for all types of accidents.
(5)
Licensee's summary statement claims-plant has the capabili.ty to continu-ously sample plant effluents for post-accident release of radioactive iodines and particulates, with onsite lab facil} ties to measure or analyze the samples.
Co-.ent:
In view of the foregoing statecant (1-4 above) by the licensee, it is suggested that this be veri.fied to ascertain that.the licensee beets the requirecents of NUREG-0737, Section~ II.F.1-2.
Assurance should be obtained that sampling and analysis cethods are adequate for sampling iodines and particulates with concen-trations up to 10 uCi/cc, as specified in NUREG-0737.
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