ML19261E405
| ML19261E405 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 05/25/1979 |
| From: | Zeff D BABCOCK & WILCOX CO. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7907060410 | |
| Download: ML19261E405 (8) | |
Text
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YDR Babcock &V!ileox
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P.O. Box 1260. Lynchbur;; Va. 24505 Telechene: (804) 324-5111
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7 g<i..1 779 United States Nuclear Regulatory Commission b'4 t
93 Office of Nuclear Staterial Safety S Safeguards
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Division of Fuel Cycle and 5!aterial Safety Washington, D.C.
20555 qq ATTENTION: 5!r. L. C. Rouse, Chief F
Fuel Processing and Fabrication Branch
REFERENCES:
(1) SN51-1168, Docket 70-1201_
(2) ? demo from !!. A. Glora to L. C. Rouse, Amendment Request 78-4, 10/13/78 (3) 5teno from W. T. Crow to D. W. Zeff,12/17/7S (4) Steno from D. W. Zeff to L. C. Rouse, 4/30/79 (5) 5temo from N. Ket:lach to D. W. Zeff, 5/22/79 Gent 1ccen:
In response to your questions and comments in Reference (5) above, we have revised Amendment Request 78-4 and are enclosing the revised pages as Attachment I to this letter.
The enclosed revision index outlines the changes that would result upon approval of the amendment.
We appreciate your consideration in this matter.
Please feel free to contact me should questions arise in the course of your review.
Sincerely, BABCOCK S NILCOX C051PANY COB 04ERCIAL SUCLEAR FUEL PLANT ye
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D. W.4 ~ c t'i, hg;e'r Safety, Licensi..;, and Safeguards DW::c=m cc: W/0 Attachments E. J. Silk J. P. hatters 7907060 %
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SNM-ll68 DOCKET 70-1201 REVISIO:t INDEX Page 1 of 2 AMEllDMEflT APPLICATION N0.
78-4 INDEX DATE:
5/25/79 Section Remove Add Reason Page
~Revisica Date Page Revision Date III 75 0
J/30/75 75 2
4/30/79 Stacked Storage Added 76 0
9/19/75 76 1
10/13/7S 7.4.4.14 Relocated IV App. 1 App. 1 Page 3 0
4/30/75 Page 3 3
5/25/79 Table Updcted App. 1 App. 1 Page 4 0'
9/19/75 Pap 4 3
5/25/79 Table Updated V
Index 1 0
4/30/75 Index 1 1
10/13/78 UO Deleted 2
15 0
9/19/75 15 1
10/13/78 Emergency Training 26 0
4/30/75 26 1
10/13/78 QA Audit Requirement Added
.281 2S]
29I 0
4/30/75 29 (.,
1 10/13/78 Redundant Table Delet3d.
30 )
- 30) Consolidated r - ;;$ 41 0
4/30/75 41 1
10/13/78 Delete Redundant gs Isolation Criteria
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9/19/75 1
10/13/78 UO Deleted 2
MunZ3 44 44 f h thru 0
4/30/75 thru 1
10/13/78 00 Deleted 2
49 s 49 gym 50 0
12/01/75 50 1
10/13/78 UO Deleted 2
51 1
5/02/77 51 2
10/13/73 UO Deleted 2
52 0
12/01/75 52 1
10/13/78 U0, Deleted S'P45 53) 53 1 0
4/30/75 54 j 1
10/13/73 UO Deleted Sh 54J 2
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55 (L~A 56-0 9/19/75 56 1
10/13/7S UO, Deleted 57) 5 7.)
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1/24/78 58 3
10/13/78 UO, Deleted 59 0
12/01/75 59 2
4/30/79 UC, 2eleted 0
4/30/75 i
1 10/13/73 UO, Deleted -
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- 7. 3. 4.1_'B Revis ed 62 0
9/19/73 62 2
2.' w/ 9 Ua, Deleted, S:'exing amy TS 0
4/30/ 3 TS 2
5/23/~9 Contamination Levels 91 0
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S!!!1-ll CS Page 2 of 2 DOCKET 70-1201 REVISIO:t liiDEX 78-4 NEllD:EliT APPLICATI0:: 40. IllDEX DATE: 5/25/79 Remove Add Reason Section~~~ Page Revision Date Page Revision Date V 92 0 4/30/75 92 1 10/13/73 UO, Deleted; QA Items Fr5m Deleted Page 28 Through 30 Added 94 1 1/24/70 94 4 5/25/79 Contamination Levels 95 1 1/24/78 95 2 in/13/78 Contanination Levels 95a 'l 1/24/78 95a 2 5/25/79 Contaminatior. Levels; 8.5 Revised Consistent h'ith DOT 101 0 4/30/75 101 1 10/13/78 8.8.4 Deleted - Redundant e e 9 13 7'1
F12TG a WILQX CGW.7/, CG:ECIAL NUCLEAR REL PUilT U5fGC LICEf;3E SN.Tll63 DOCKET 70-1201 i IV HEALTH PHYSICS APPErlDIX 1, Page 3 SECTIG4 SUf' MARY OF SELECTED HEALTH PHYSICS CRITERIA 0. EXTERNAL 00SI!1ETRY (continued) 4. fleutron 00simetry a. Application - Personnel utilizing neutron generating devices - Determined by Health-Safety b. System - Film, vendor supplied c. Frequency - Monthly change or more fre-quently, if required 5. Criticality Dosimetry a. Personnel - Indium foil incorporated in TLD/or ID badge b. General - Criticality dosimeters placed throughout plant - Contains AU, IN, S, TLD and glass dosimeters - Analytical capability available on site. C. SURFACE CONTAf1IflATI0ft CONTROL Items 1, 2, and 3 of this section represent contanination levels which, when exceeded, will cause clean-up activities of the affected area to be initiated. 1. Controlled Areas 2 a. Removable = 5,000 DPM/100 cm 2 b. Total = 50,000 DPM/ 50 cm y ep" - Weekly Survey Frequency,0 m ^ 39 c. IIw, n ~ g. ?G Pe b gm Q'f'(\\[.3, y s h*., (,,'; ' ' '")
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B/JCCC' & WILOM CGP/M, CG;ZT,CIAL ICLE/2 Fu1 PUiff USl,RC LICE!.3E S,l'.-1153 LC,CYET /u-E]l SECTICri IV HEALTH PHYSICS APPEilDIX 1, Page 4 Sut?tARY OF SELECTED HEALTH PHYSICS CRITERIA C. SURFACE C0tiTAMIriATI0tl CO:iTROL (continued) 2. Change Rooms (Intermediate Area) 2 *** a. Removable = 500 DPM/100 cm 2 b. Total = - 2,000 CPM / 50 cm c. Survey Frequency - Daily when in operation 3. General Plant Area a. Acceptable average 2 removable = - 200 DPM/100 cm 2 b. Total = - 500 DPM/ 50 cm c. Survey Frequency - Monthly or more frequently*"* as required (daily in cafeteria and locker rooms) 4. Materials and Equipment a. Transferred from controlled 2 area - 100 DPM/100 cm removable *** for unrestricted release - Higher levels under special controls by Health-Safety b. Survey Frequency - As requ. d. 5. Waste and Scrap for Unrestricted Release 2 a. Maximum Removable = 1 1000 CP'/100 cm 2 b. Maximum Total = -< 7,500 DPM/50 cm 2 < 2,500 DPM/50 cm c. Average Total = d. Beta & Gama $ 1 mrad / hour (Average 0.2 mrad /hr.) e. Survey Frequency - Monthly or more frequently as required. -s" 79 -- e' /_ \\ ' '{, f f l',,;s.[ .q'.;y i' .j . /. 7 ; t, ; t. 't -i
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B/BCDCK & WILCOX CGWin', CG;ZFLl/L lRHEAR FEL PililT usurc ucEnsE sta-lE3 DnET 70-lTA ,SECTICr4 V C0flDITIO!!S 8.0 Technical Soecificati_ons - Radiation Safety 8.1 Eff 7 rnts to 'Jnrec t ':'"d Areas 8.1.3 The following parameters are established for determining if waste or excess materials and equipment may be disposed of in routine industrial fashion. If any of the specifications set forth below are exceeded, the m.aterial will be controlled as contaminated. a. The maximum total alpha contamination will not exceed 7,500 disintegrations per minute per 50 square centimeters. Total contamination shall be defined as fixed + removable. b. The average total alpha contamination on any item of waste or equipment will not exceed 2500 disintegrations per minute per 50 square centi-meters. c. The maximum alpha contamination removable by wipe will not exceed 1000 disintegrations per nJnute per 100 square centimeters. d. Beta + gamna radiation levels when measured with an open shield, thin-tube wall GM survey instru-ment at one centimer will not exceed a maximum of one millirad per hour, nor an average of 0.2 mrad /hr. ~ ~ ~~ ~~ Q 7! ') z e i 12 i 7 [ ! , "i - q my l
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E/ETO' a WILCCX CCPl."Y, CCZ!/l. "'JOHa REL PLG LC;P.C LICEi:E S!;.'Pll60 ELC's 70-01 SECTim V CONDITIONS 8.0 Technical Specifications - Radiation Safety 8.3 Instru.antation (continued) 8.3.4 All instrumentation will be calibrated upon initial installation, following major maintenance, and at other times as deemed necessary. In any case, calibration will be performed at least semi-annuall.v. Laboratory counting instruments shall be calibration-checked daily when in use. 8.3.5 Field check sources will be available for assuring functional response of instrumentation prior to use. 8.4 Personnel Monitoring and Contamination Control 8.4.1 Personnel monitoring equipment - film badges, thermo-luminescent dosimeters, detectors, etc., - will be used by persons having access to restricted or radi-ation areas, as deemed necessary by Health-Safety, and in accord with 10 CFR 20. The dosimeters will be processed routinely to determine radiation dose. Health-Safety will review and maintain the dose records and prepare such reports as are required by regulations. Neutron dosimeters will be used by operators and other persons as deered nacessary by Health-Safety when a potential for measurable neutron exposure exists. ir '} ~~ ~- C '3/79 ' ~: 91 ') C' ' T D'.'! S I C' : c. .. ___...:2 'I L... ~ u. -. 4L FZ.T. _..;2 ?-- 7-p op.e r,.,.
B;GGG( & WILQX CG?iM, CG.MI/1 NUCifla FLEL PL/nT UCI C LICEf;5E St;lt-ll60 IX)CKET 70-1201 SECTim V CONDITIONS 8.0 Technical Specifications - Radiation Safety 8.4 Personnel Monitoring and Contanination Control 8.4.4 Personnel Contamination 8.4.4.1
- a. - Survey anti-contamination clothing, if con-tamination levels are more than 350 but less ***
d than 3500 DPM/50 cm, or equivalent, don clean protective clothing over the contami-nated garments. Anti-contamination clothing with contamination levels greater than 3500 DPM/50 cm', or equivalent, shall be removed. *** - Remove shoe covers worn in controlled areas, or place clean shoe covers over contaminated shoes.
- b. Other than as noted above, use of anti-contami-nated clothing for temporary or non-routine activities shall be as stated in Paragraph 8.4.6 of this section.
8.4.5 Surface Contamination Control The following criteria shall be applied to the monitoring ..J and control of surface contamination. The levels shown below *** 5,[ represent contamination levels which, when exceeded, will cause clean-up activities of the affected area to be initiated.*" Area A-* .-e te a1 prveyTreLecy e '. D c-! ' MIY 1. Centrolled Mllet tr :.atle: L'O' ' l L 3 cr ' (str1 cath-fr32
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Cha-e Ocn P--ovabie: 53 ryt3 c 2 C211y* (Ir.terediate) Total 2.0C] CT */ 50 c: 2
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p'a-t a-: cffice area) The lunchrcon and locker rec ~s shall be surveyed daily wha: + in use and renov2ble contanination kept as low as reasonably '; M ibbachie'.abla. c/o e aq-,-+ Q 'g U/-- C,,v, l, ^ ~, ._ ; ; i ~ p _ ' _.,_ _. m:0
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P12CO' 8 WILQX CCi?/ B', CC Elft NL'QBa REL PL/#T (E*;RC LICE :SE SN"-13E3 DoCyrT70-151 SECTIQ1 V C0fiDITIONS 8.0 Technical Soecifications - Radiation Safety 8.4 Personnel Monitorino and Contamination Control 8.4.6 Continued - During the course of the operation decontamination will be initiated when general contamination levels in excess of 1000 DPM/100 cm2(removable)or2000 DPM/50 cm2 (total) are noted. Following completion of the operation, decontamination to clean area levels specified in Paragraph 8.4.5 shall be accomplished. ~8.5 Receivino Insoection 8.5.1 SNM receipts will be inspected for damage, and surveys conducted to ascertain if the level of contamination is acceptable for CNFP handling und storage. Results in excess of contamination limits specified by the Department of Transportation will be reported to Health-Safety for noti-cation of the shipper and evaluation of the need for decontamination. 8.6 Non-Exer.ot Sealed Source Control 8.6.1 Use of non-exempt sources for training and instrument calibration shall be limited to, or under the direct control of, qualified Health-Safety personnel. 8.6.2 Sources utilized as a functional component of devices n ts 7.b } }.' f n' r' 733 d p-.-. c. -E2.=dc'.^ ': ~ ~ n i ', %+ yn ~ + l. .; ~ : la.?, J ~. /sL F.~.1 .....}}