ML19318B008
| ML19318B008 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 05/06/1980 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML19318B007 | List: |
| References | |
| 16273, NUDOCS 8006240518 | |
| Download: ML19318B008 (9) | |
Text
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DOCKET 70-1201 REVISION IllDEX AENDffitT APPLICATI0ft fi0.
79-3 INDEX DATE:
5-06-80 Section Remove Add Reason Page Revision Date Page Revision Date III 194-195 0
4/30/75 194-195 1
5-06-80 Revised interaction V
25 0
4/30/75 25 1
5-06-80 Wording change V
69 0
12/01/75 69 1
5-06-80 Revised interaction V
70 0
12/01/75 70 1
5-06-80 Revised interaction Y
76 0
4/30/75 76 1
5-06-80 Air action level change V
77 0
4/30/75 77 1
5-06-80 Water action level change
]
V 94 0
5/25/79 94 1
5-06-80 Revised contamination survey frequency
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BABG)0( & WILQX C&P#ff, QMERCIAL NUGER REL PlM uSNRC U NSE SNtt-ll68 DOCKET 70-1201 SECTim III NUCLEAR SAFETY ANALYSIS 7.'10 fuel Assembly Storage 7.10.1 Continued Interaction:
The 21 x 38 inch c/c array is the more reactive. Since it has been assumed infinite in the x-y plane, its calculated k-effective is higher than that of the combination of the two arrays. The separa-tion between the two arrays is greater than 38 inches so that no third type of array is created.
Therefore, values obtained for the infinite 38 x 21 inch c/c array may be conservatively used for the actual combination. For the maximum credible degree of interspersed moderation, k-effective is
- 1ess than 0.4.
Similarly, all other arrays not isolated from the assembly storage array are also free draining and cannot accumulate low density moderator. Since they are also low enriched uranium
(_<,4 weight %) the same principle applies--the actual combination of arrays is less reactive than the infinite array of 38 x 21 inch c/c assemblies.
1 l
7.10.2 Sectica III, Part 7.10.1 discusses the nuclear safety of an infinite array of parallel ' fuel assemblies stored in 21 inch by 38 inch or 36 inch center-to-center spacing in a vertical con-I figuration.
Part 7.9 validates the nuclear safety of fuel as-sembly processing.
Huclear interaction between fuel assembly processing and assembly storage is limited to less than the in-teraction within the storage array alone due to geometric relation-ship. Nuclear interaction between assembly storage and assembly shipping container loading is limited to the interaction associ-ated with an array of damaged loaded shipping containers as described on Pages 196-200 of Section III of this part..Since a planar array of assemblies on 21 inch centers is subcritical for credible interspersed moderation conditions (Part 7.10.1)
(Part 7.10.1), the planar array in the assembly I94 MTE 5-06-80 REVISIM NO.
1 PAGE CLRREtR REVISION:
SUPERSEDES: PAGE l94 USNRC APPROVAL. REFERENCE MTE 4/30/75 REVISION O
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BABQXX & WILGR C&PANY, C[MERCIAL NUC1 EAR REL PUNT LENRC UCENSE S!@t-ll68 DOCKET 70-1201 SECT!m III NUCLEAR SAFETY ANALYSIS 7.10 Fuel Assembly Storage 7.10.2 Continued processing area, where four foot separation is maintained, is likewise suberitical. Two or more planar arrays have been l
shown to be suberitical in combination when center-to-center distance is not less than 38 inches, and with major faces opposed, the situation resulting from consideration of an infinite storage array.
j Rotation of one planar array 90 degrees from the vertical to present its edge to the face of the opposing array, while main-taining the specified separative distances', significantly reduces interaction probabilities by presenting less " effective" surface area for interaction thus,.in effect, extending the effectiva separation distance. This demonstration accurately reflects conditions at the junction of the fuel assembly pro-cessing and storage area, and also at the junction of the assom-bly storage and shipping container loading area.
Under nonnal operating conditions the activities will be con-ducted in the absence of any significant moderation; under such conditions, fuel of 4 wt.% enrichment and less cannot be made critical.
MTE 5-06-80 REVIS! W NO.
1 PAGE 195 CLRRENT REVISION:
SUPERSEDES: PAGE 195 USNRC APPROVE REFERENCE MTE 4/30/75 REVISION O
l MBOXX & WIL(DX C00fff, CutEIEIAL NUQfAR REL PIM USNRC U NSE SNPt-ll68 DOCKET X)-1201 V CONDITIONS SECTICN 6.0' General Specifications 6.6 Procedure Control (continued)
- Procedures developed by Health-Safety specifying the method by which safety related functions are to be accom-p11shed. Such procedures may be for internal Health-Safety use or may be intended for general distribution to affected individuals within other components.
Health-Safety proce-dures shall be approved in writing by the Plant Manager, the Manager, Health-Safety and Licensing, and other members of plant management / supervision if it is determined by Health-Safety that their area of responsibility is affected by the procedure.
- Safeguards procedures provide tech-niques for the accountability and measurement of SNM. Such procedures will be approved in writing by the Manager, Health ***
Safety and Licensing and by affected plant management.
- Manufacturing, Quality Control, and selected Maintenance /
Engineering procedures, where nuclear or radiological safety, license conditions, or regulatory requirements are involved t
require prior approval by the Manager, Health-Safety and Licensing, as well as approval by affected members of i
plant management.
2 I
MTE 5-06-80 REVISIOl NO.
PAGE 25 CLRRENT REVISION:
SLPERSEDES: PAGE 25 USNRC APPR R ETERENCE MTE 4/30/75 REY!SICN 0
.,4
BE00( & WILE)X C&PANY, QMERCIAL NUC1 EAR REl. PLM USNRC LI NSE SNM-ll68 DOCKET M-1201 SECTIm V CONDITIONS 7'0 Nuclear Safety - Technical Specifications 7.9 Fuel Assembly Processing (cont'd) 7.9.1 Continued accumulation of fuel rods once the fuel rods have been removed from the geometric safe 4.0" slab.
A minimum separation of 4 feet will be maintained be-tween bundle assembly stations, and the equipment will be such that liquids cannot be retained in and around the in-process operation.
7.9.2 Assembly processing operations once the fuel rods are restrained in the fuel assembly configuration may be perfonned without moderation control. The assemblies will be separated by at least 36" center-to-center.
7.9.3 For the purposes of nuclear interaction control, the fuel assembly processing and fuel assembly storage arrays are censidered as a single array with adjacent arrays being no more reactive than an array of fuel assemblies loaded in adjacent containers as described in Part 7.10.3 of Section V.
7.10 Fuel Assembly Storage and Packaging 7.10.1 Fuel assembly dust wrappers, if used, will be arranged to pennit dra^nage of water from within. Moderation, such as polyethylene, etc., will not be permitted within the assettlies.
DATE 5-06-80 I
PE 69 REVISI m NO.
CtRRENT REVISIm:
SUPERSEDES: PAGE 69 G RC N A RE N G m7s 12/1/75 0
REVISIm
BABG)0( & WILCDX C&PM, CGtERCIAL NlufR REL PLA1T USNRC UC9tSE Sitt+-ll68 DOCKET 70-1201 SECTICH V C0flDITI0 tis
- 7. 'O Nuclear Safety - Technical Specifications 7.10 Fuel Assembly Storage and Packaging (continued) 7.10.2 Fuel assemblies may be stored in racks meeting the following spacing criteria:
a.
Fuel assemblies in linear arrays will have mini-mum 21" center-to-center spacing.
b.
Fuel assemblies in planar arrays will be arranged on minimum 36" x 36" center-to-center spacing.
c.
A minimum of 38" center-to-center spacing will be maintained between the nearest assemblies of adjacent planar of linear storage arrays.
The following restrictions shall be imposed on fire fighting within the assembly storage array:
a.
The use of hoselines shall be prohibited unless authorization has been received from a management representative of the plant emergency response organization.
b.
Area postings will be maintained at the array perimeter specifying limitations on fire fight-ing techniques.
c.
Simultaneous application of more than ene hoseline is not authorized.
7.10.3 Fuel assembly packaging and unpackaging operations involving licensed Model B shipping containers will be performed within the following limitations:
a.
Fuel assembly packaging will be in accord with the requirements of the container certificate.
b.
Fuel assemblies in adjacent containers will be separated by not less than 18 inches edge-to-edge.
c.
Fuel assembly loading operations will be separated by a minimum of 38" center to center from adjacent fuel assemblies in the storage rack.
DATE S-06-80 REVISION NO.
1 PAE 70 CtRRENT REVISION:
SLPERSEDES: PAGE 70 USNRC APPROVAL EFERENCE DATE 12/1/75 REVISICN 0
.I B2CDO( & WILQX CEPAW, C0fBCIAL NUCLEAR REL PUM IJSNRC LICENSE SfM-ll68 DOCKET 70-1201 V CONDITIC1S SECTICN 8.0 Technical Specifications - Radiation Safety 8.1 Effluents to Unrestricted Areas 8.1.1 Continued c.
The following program shall be instituted to assure that airborne releases to uncontrolled areas are main-tained as low as practicable:
Quarterly Average - % of 10 CFR 20
- u*
Appendix B, Table 2 LIMIT ACTION 1 10% of "MPC" None required.
11 - 20%
Conduct investigation of system and correct if possible.*
21 - 75%
Visually inspect system. As soon as practicable, conduct efficiency I
test. Detemine and correct cause.**
> 75%
Conduct imediate investigation to determine and correct problem in ventilati.on system. Maintain addia tional Health-Safety surveillance of system to monitor contamination levels until problem is corrected.
end weld operation area - None required end weld operation area - flone required at 1 50% !!PC
- x*
Health-Safety shall maintain records of investiga-tions and actions resulting therefrom, d.
Pre-filters serving equipment in the pelletizing area will be instrumented and monitored as speci-fied in 8.1.la above.
8.1.2 Potentially contaminated liquid effluents wi;l be controlled through a retention tank system with dilution and mixing capabilities and shall be evaluated DATE 5-06-80 REVISIGI NO.
I PAGE 76 CtRRENT REVISION:
SUPERSEDES: PAGE 76 WNRC N E RE M &
DATE 4/30/75 REVISim 0
MIKDO( & WIL(DX C&PM, Cut 9CIAL NtX1 EAR REL PLM USNRC LICENSE SNM-ll68 DOCKET M.1201 V C0fiDITI0tlS SECTim 8.'O Technical Specifications - Radiation Safety 8.1 Effluents to Unrestricted Areas 8.1.2 Continued for compliance with 10 CFR 20, Appendix B limits prior to release to unrestricted areas.
The folicwing actions, at the contamination levels indicated, will be undertaken in order to maintain contaminated liquid effluent re-leases as low as practicable:
% 10 CFR 20 App. B. "MPC" Action
< 20%
No action required.
21 - 75%
Individual releases authorized
.by Plant Manager or his alter-nate.
> 75%
Discharge prohibited. Waste routed for further treatment or disposal by burial.
Health-Safety shall maintain records of investigations and actions resulting therefrom.
a.
Retention tanks will be inspected monthly for sludge accumulation.
l MTE 5-06-80 REVISION NO.
I PAGE 77 l
l CLRRENT REVISIN:
l SLPERSEDES: PAGE 77 M APPR R REFEREN MTE 4/30/75 REVISION O
BABGXX & WILCDX COP #ff, CatERCIAL NUCLEAR REL PLMiT USNRC UCENSE SNM-ll68 DOCKET 70-El SECTICN V CONDITIONS 8.d Technical Specifications - Radiation Safety 8.4 Personnel Monitoring and Contamination Control 8.4.4 Personnel Contaminatior, 8.4.4.1 ~ a. - Survey anti-contamination clothing, if con-tamination levels are more than 350 but less than 3500 DPM/50 cm2, or equivalent, don clean protective clothing over the contami-nated garments.
Anti-contamination clothing with contamination levels greater than 3500 DPM/50 cm2, 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.
'I 8.4.5 Surface Contamination Control The following criteria shall be applied 'to monitoring and control of surface contamination.
The levels shown below represent contamination levels which, when exceeded, will cause clean-up activities of the affected area to be initiated.
Aree Actfee tevel Survey Freeuency d'.cuu at oal d V
on loading ch. age esce (het area)
- 2. thange anos a
..bter 2
soo tr tno0 c.2 notty.
(Interzediate)
Total 2.000 DM V 53 cm "When po.eder processing c;erations (not includit; ros,tice quality control activities) are being conducted. Ja yo pse will there be more than t,ne week bet.een surveys.
3.
Cleas Renovable:
200t~.f*'.c/
Fathly (Rasainder of Total 54 C 4 plant and office
~
a The lunchroom and locker rooms shall be surveyed daily when in use and removable contamination kept as low as reasonably achievable, y
I DATE 5-06-80 REVISION NO.
S'
.lPAGE 94
- Added CURRENT REVISION:
^t,'*7 ' -
4 SUPERSEDES: PAGE 94-
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USNRC APPROVAL REFERENCE DATE 5/25/79 REVISICN 4_ _ _.
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