ML20041C096
| ML20041C096 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 01/29/1982 |
| From: | Jennifer Ford BABCOCK & WILCOX CO. |
| To: | Page R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20041C097 | List: |
| References | |
| RTR-REGGD-08.005, RTR-REGGD-8.005 20227, NUDOCS 8202260182 | |
| Download: ML20041C096 (19) | |
Text
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s ye /2o I Babcock & Wilcox suci..r u.t.ri.i. a u nut.cturin or a McDermott compa (J
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P.O. Box 800 W
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Lynchburg, Virginia 24505
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Division of Fuel Cycle and Material Safety x
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REFERENCES:
(1) SNM-1168, Docket 70-1201, License Renewal App 1'ef lon dated 2-27-81 D J'C;~ -
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(2) Letter from Norman Ket::lach to Dave Zeff, dat [
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10-21-81
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(3) Letter from J. T. Ford to R. G. Page, dated 9
'D'y 43-7-81
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Gentlemen:
t In regards to your questions and comments (Reference 2) on our license renewal application, dated 2-27-81, the Babcock 6 Wilcox Company, Commercial Nuc1 car Fuel Plant submits the additional information needed to complete your evaluation.
Attachment I to this letter is a copy of the American Nuclear Insurers Inspection report.
Attachment II to this letter is a copy of the Factory Mutual Inspection report.
Attachment III to this letter is seven (7) copies of the changed pages of our license renewal application.
Please make the following page substitutions:
Delete Following Pages Add Following PagesSection I Dated 2-27-81 Section I Dated 1-29-82 2
2 5
5 7
8 9
4 Appendix A 10,7 5
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's- ' I; 6
c 7
o a
v' 8
y 9 Appendix A 8202260182 820129 PDR ADOCK 07001201 C
PDR j
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Babcock &Wilcox United States Nuclear Regulatory Commission Page 2 l
January 29, 1982
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Delete Following Pages Add Following Pages
.ection III Dated 2-27-81 Section III Dated 1-29-82 Index Index 13 Appendix A 2
2 15 4
4 16 5
5 17 13 13 18 i
34 34 19 y
39 39 20 Appendix A 41 41 1 Appendix B 42 42 1 Appendix C 43 43 67 67 68 68 69 69 70 70 71 71 77 77 78 78 83 83 84 84 105 105 106 106 111 111 114 114 129 129 131 131 138 138 147 147 150 150 152 152 153 153 158 158 159.
158a 160 159 176 160 177 176 181 177 190 181 13 Appendix A 190 i
15 191 1
16 192 17 193 q
18 Appendix A 194 1 Appendix B 195.
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Babcock &Wilcox United States Nuclear Regulatory Commission l
Page 3 l
January 29, 1982 I
Delete Following Pages Add Following PagesSection IV Dated 2-27-81 Section IV Dated 1-29-82 1
1
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9 9
14 14 17 17 i
25 25 35 35 44 44 4 Appendix 2 4 Appendix 2 5
6 App'endix 2 Delete Following Pages Add Following PagesSection V Dated 2-27-81 Section V Dated 1-29-82 I Index 33 65 1 Index 33 65 3
34 66 3
34 66 i
6 35 67 6
35 67 7
36 68 7
36 68 8
37 70 8
37 70 9
38 71 9
38 71 10 39 72 10 39 72 11 40 73 11 40 73 12 41 74 12 41 74 13 44 75 13 44 75 14 47 76 14 47 76 15 48 77 15 48 77 16 49 78 16 49 78 17 50 79 17 50 79 18 51 80 18 il 80 19 52 81 19 5.1 81 20 53 82 20 53 82 21 55 83 21 55 83 22 56 84' 22 56' 84 23 57 85 23 57 85 24 58 86 24 58 86 25 59 87
.25 59 87
-26 60 88 26 60 27 61 89 27 61 28 62 28 62 29 63 29 63 32 64 32 64 4
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1 Babcock &Wilcox I
i United States Nuclear Regulatory Commission Page 4 January 29, 1982 The following is provided as a guide to aid in your review of our responses to your questions:
I.
License Conditions i
A.
Section V i
1.
See Figures 1 and 2 of Section I for plant and site
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i layout.
I 2.
See Section III, Part 7.17 and Section V, Part 7.17 i
for demonstration and storage criteria for enriched UF. See Section I, Figure 1 for location of UT 6
6 storage area.
l 3.
See Section IV, Appendix 2, Page 5 for clarification of contamination quantities on returned, unirradiated fuel components.
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4.
See Figure 3 of Section I and Part 5.1 of Section V for 1
organizational chart.
5.
The Safety Review Board is the ALARA committee and is committed to the "ALARA principle" as stated in Section V, Part 6.1.1.
An annual report shall go to the Safety Review Board as stated in Section V, Part 6.6.
l The maximum bFC hours per quarter for the last two years are listed in Section IV, Part 8.7, Figure 1.
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6.
Additional resumes are included in Section I, Appendix A.
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7.
The independent auditors are the responsibility of and are designated by the Plant Manager,Section V, Part 7
5.4.2.
i I
8a.
System efficiency shall be evaluated at least annually,Section V,' Part 8.1.1.
j b.
Quarterly air sample program records are reviewed by the Manager,llealth-Safety and Licensing,Section V, Part 6.1.
I
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Babcock &Wilcox i
United States Nuclear Regulatory Commission r
Page 5 January 29, 1982 l
I.
License Conditions A.
Section V (cont'd) 8c.
The Health-Safety Supervisor or qualified designee as appointed by the Manager, Health-Safety and Licensing,Section V, Part 6.1.
d.
The Manager, Health-Safety and Licensing shall decide whether or not the necessary disciplines are present i
during a Board meeting to evaluate the item (s) under l
consideration. There shall be a minimum of four Safety i
Review Board members present during a Board meeting,Section V, Part 6.1.1.
e.
The Manager, Health-Safety and Licensing may order the i
operation suspended,Section V, Part 6.1.
b 9a.
Changed ALAP to ALARA,Section V, Part 6.1.1.
i b.
A " minor change" means that the existing safety practice i
remains the same,Section V, Part 6.1.1.
t c.
Permanent membership of the Board shall be specified by procedure, which is approved by the Plant Manager,
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Section V, Part 6.1.1.
d.
A properly documented nuclear safety evaluation performed
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by the NCSG shall include a quality assurance statement, 3
Section V, Part 5.S.3.
j e.
The Manager, Health-Safety and Licensing shall review the audit reports as they are submitted and actions which are necessary because of audit findings shall be documented,_Section.V, Part 6.6.
f.
The Manager,' Health-Safety and Licensing reviews all I
requests for changes in process and equipment and determines if Board review is necessary. Safety Review Board members shall be kept appraised of actions taken by the Manager, Health-Safety and Licensing on such-minor changes,Section V, Part.6.1.1.
Babcock &Wilcox United States Nuclear Regulatory Commission l
Page 6 January 29, 1982 1.
License Conditions
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A.
Section V (cont'd)
I 10a. Operating logs and records of reviews, tests, inspections, personnel qualifications, and audits shall be maintained i
on file for a minimum of two years or as otherwise required by federal regulation or other license conditions, I
Section V, Part 6.1.2.
- b. Initial indoctrination of employees into nuclear and radiological safety shall be the responsibility of
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Health-Safety, and shall conform with 10 CFR 19, Section V, Part 6.2.
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- c. Documentation of formal training and retraining is main-tained by Health-Safety,Section V, Part 6.2.
J lla. Management assurance is described in Section V, Part 5.3.
I
- b. The training and retraining programs are evaluated through 7
methods stated in Section V, Part 5.3 and 6.6.
12.
Health-Safety monitoring personnel shall receive a combina-tion of formal and. "on-the-job" training such that they can successfully demonstrate their' proficiency in basic nucicar and radiation physics monitoring and control i
techniques and regulatory requirements before being allowed to function without direct oversight,Section V, Part 6.2.
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13a. Administrative controls are described in Section V, Paragraph 6.1.1.
1
- b. Applicabic procedures shall be available in the work area, i
Section V, Part 6.5.
I 14a. At least weekly, a formal audit of plant status shall be ~
conducted relative to nuclear and radiological safety.
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At the discretion of Health-Safety, the audit may consist -
of an indepth evaluation of a specific area (fire, environmental quality),Section V, Part 6.6.
Section III, Part 7.4.5.1.7.
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Babcock &Wilcox United States Nuclear Regulatory Commission Page 7 i
January 29, 1982 c
I.
License Conditions l
'A'.
Section V (cont'd) t 14b. The Manager, !!ealth-Safety and Licensing
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I shall review the audit reports as they are sub-mitted,Section V, Part 6.6.
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- c. Actions which are necessary because of audit i
findings shall be documented,Section V, Part 6.6.
- d. All formal (quarterly) nuclear safety and health physics audits shall be conducted in accordance with written instruction and/or procedure,Section V, Part 6.6.
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- e. Contamination survey data is taken in accordance with Section V, Part 8.4.5.
The survey data is reviewed in acco~rd with the survey frequency.
- f. A minimum of 2 years or as otherwise required by federal regulation or other license condi-tion,Section V, Part 6.1.2.
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Babcocka,Wilcox United States Nuclear Regulatory Commission Page 8 January 29, 1982 I.
License Conditions A.
Section V (cont'd) 15.
Unusual events which require reporting under 10 CFR shall be investigated, with results reported to plant management and NRC,Section V, Part 6.7.
16.
The SANGLE code writeup in Section III, Appendix A states that all units are considered and shadowing is neglected.
The demonstration in Section III, Part 7.4.2.13 was redone.
17.
Safe volume is defined in Section III, Part 7.4.2(b) and Section V, Part 4.9.
18.
Flammable wastes are accumulated in covered fire-safe containers,Section V, Part 7.4.3.1(F),Section III, Part 7.4.S.I.3.
19.
The maximum allowable moisture content in the powder shall be 2 weight percent,Section V, Part 7.4.4.1(c).
20.
Typographical error, changed to 28 inches,Section V, Part 7.4.4.14(f).
21.
All accumulations shall be within the confines of a 6 foot slab, with no accumulation positioned above or below another accumulation,Section III, Part 7.7.1(b).
22.
A demonstration of the effect of using 0.3 fraction critical mass in conjunction with a smeared thickness of 2.3 in, surface density calculations is provided in Section III, Part 7.7.2.
23.
40 CFR 190 license condition included in Section V, Part 8.1.1(d).
24.
An environmental monitoring program shall be conducted as shown in Section V, Part 8.1.4.
25.
Changed ALAP to ALARA,Section V, Part 8.2.2.
Babcock &Wilcox United States Nuclear Regulatory Commission i
Page 9 January 29, 1982 I.
License Conditions A.
Section V (cont'd)
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26.
Hood velocities of less than 100 LEM shall not be used unless it can be technically justified using air sampling techniques on a case-by-case basis and specifically approved by Health-Safety supervision,Section V, Part 8.2.2.
27a. Air samples shall be collected after each shift,Section V, Part 8.2.3.
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- b. If any one sample measures 100% MPC, the location and occurrence shall be investigated,Section V, Part 8.2.3.
- c. Air samples shall be collected that are representative of the air which the worker is exposed to.
Work station air samplers shall be positioned to provide for evaluation of airborne levels at the work station,Section V, Part 8.2.3.
28.
Respiratory protective equipment shall be governed by i
Regulatory Guide 8.15,Section V, Part 8.24.
29.
Response time for the system shall be in accord with Regulatory Guide 8.5, " Criticality and Other Interior l
Evacuation Signals", dated March, 1981,Section V, Part 8.3.3.
30.
Health-Safety shall be notified when initial decortamina-tion attempts fail to reduce skin contamination to e
acceptable levels and will assist during further deconta-mination, as necessary, to Icvels as low as practicable, consistent with good health physics practice before releasing the employee,Section V, Part 8.4.4.
31.
When contamination levels are exceeded, prompt cleanup activities will be initicted,-Section V, Part 8.4.S.
32.
Inserted "shall" in place of "are" or "will" wherever appropriate.
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Babcock &Wilcox P
United States Nuclear Regulatory Commission Page 10 January 29, 1982 i
I.
License Conditions B.
Safety Conditions Not Addressed 1.
The CNFP policy is stated in Section V, Parts 5.1, 5.3, and 6.1.1.
2.
Clarification of the Radiation Work Permit program is provided in Section IV, Part 17.2.
II.
Demonstration Sections i
A.
Section I
{
1.
Deleted Figures 1 and 2 from the application.
E 2a.
Changed low enriched uranium as other than oxide to (a)(4I.and uranium as natural uranium as low enriched UF UF,Section I,'Part 6
b.
Refer to Section V, Parts 8.2 and 8.3.
t c.
Refer to Section V, Part 6.5.
3a i
b.
All cre identified in Section I, Page 6.
c.
4.
Resumes of personnel. with safety related responsibilities are included in Section I.
B.
Section II la.
Fred G. Welfare, November 1973, Page 268 is the completed Reference 1,Section III, Part 7.1.2.
b.
Completed the equation for the interaction fraction (p),
Section III, Part 7.1.2.
c.
Identified interaction items a, b, and c,Section III, Part 7.1.2.
2.
Replaced graph in Section III, Part 7.1.2.
o r,h.
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Babcock &Wilcox United States Nuclear Regulatory Commission Page 11 January 29, 1982 II.
Demonstration Sections B.
Section II (cont'd) 3.
Identified items d and e,Section III, Part 7.1.2.
4a.
Provided flowsheet, Figure 1, Appendix C,Section III.
b.
Replaced Pelletizing Layout, Appendix B,Section III.
Sa.
Deleted, this array is not used.
b.
Deleted, this array is not used.
The applicability of the solid angle method for low enriched c.
UO -water mixture is demonstrated in TID 7016, Rev. 2.
2 d.
Deleted, this array is not used.
6.
SANGLE code writeup,Section III, Appendix A.
7.
Solid angle is calculated from each unit, allows selection of most reactive unit,Section III, Part 7.4.2.9.
8.
The reference to sprinkler spray density has been deleted from Section III, Part 7.4.3.
9a.
Figure 2 is in Part 7.4.2.3, stated in Section III, Part 7.4.4.1.
b.
Figure I is in Part 7.4.2.2, stated in Section III, Part 7.4.4.1.
10.
Corrected the weight percent of sterotex,Section III, Part 7.4.4.1.
11.
The total hydrogen measurement instrument is an effective technique for the periodic measurements required to determine total 11 content,Section III, Part 7.4.4.6.
2 Corrected to read, "by a second qualified individual",
12.
Section III, Part 7.4.4.7.1.
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Babcock 83Milcox ~
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United States Nuclear Regulatory Commission Page 12 l
January 29, 1982 I
I II.
Demonstration Sections i
B.
Section II (cont'd)
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13.
Accumulations of flammable wastes and scrap are removed from the area promptly when containers are filled, j
Section III,.Part 7.4.S.I.3.
14.
Corrected the clad thickness,-Section III, Part 7.S.1.2.
1 15.
Corrected to read, ' acceptable interaction between the pellet vault and all other SNM storage or handling areas is assured by means of 8 inch solid concrete walls",
Section III, Part 7.5.3.B.
f 16.
Changed title of last column to Slab Thickness Equivalent.
of 0.3f Critical Sphere,Section III, Part 7.6.2.
17.
Corrrected the fraction critical and slab thickness ratios, r
Section III, Part 7.7.2, Application of Surface Density.
i 4
18.
References 1 through 5 are listed in Section III, i
Part 7.7.1.
19.
Changed to read Slab Thickness Equivalent to 0.3f Critical Sphere,Section III, Part 7.7.
f 20a. The reference to a one-inch fog nozzle has been removed i
from Section III, Part 7.10.1.
I
- b. The reference to the sprinkler system has been removed r
from Section III, Part 7.10.1.
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s 21.
The KENO code is summarized.in Section III, Appendix A.
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i 22a. The buildings were built in accord with V'irginia Fire Safety Code (1968). The facilities are operated in j
accord with Section IV, Part 18.2 and Section V, Part 8.8.
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- b. A copy of the latest ANI and FM reports are provided as attachments to this letter.
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i Babcock &Wilcox United States Nuclear Regulatory Commission i
Page 13 January 29, 1982 II.
Demonstration Sections P
C.
Section IV 1.
The CNFP " policy" is incorporated in Section V, Parts e
5.1 and 5.3, and 6.1.1.
The Manager, Health-Safety and Licensing may suspend operations per Section V, Part 6.1.
Thank you for your attention to this matter.
If there are any questions during your review, please call me at (804) 522-5966.
Sincerely, t
BABCOCK & WILCOX COMPANY COMMERCIAL NUCLEAR FUEL PLANT J. T. Ford License Administrator JTF:cmr Attachments f
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R. A. Alto D. W. Zeff i
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ATTACHMENT 1
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ENGINlERING DEPARTMENT Leo P Mfoni. Vice President
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BURT C.PROOM.CPCU President June 26,1981
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Mr. David W. Zef f, Manager F
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Babcock & Wilcox Commercial Nuclear Fuel Plant P. O. Box 800 Lynchburg, VA 24505 RE: ANI Inspection May 19, 1981 NF-111, CNFP
Dear Dave:
Both Roger Waite and I appreciated yours and Ray Vinton's time and cooperation during our May 19, 1981 inspection. The areas which were reviewed in the course of this inspection included: Dosimetry of Personnel; Records Retention Practices; Eavironmental Monitoring; and Control of Effluents.
A few recommendations developed as a result of our discussions and tour of the facility.
Since the detector is worn on top of the finger, the question as to how representative the dose as shown by the rings is to the actual dose was questioned.
it was therefore recommended:
81-1 The finger dose as given by the finger rings be confirmed as being representative of the exposure to the skin on the inside of the fingers.
A review of your radiological safety related records showed them in general to be in good order. Certain areas however needed to be upgraded.
in particular, a method to store these records so they will not be lost in the event of a fire.
Other records retention practices that were discussed included:
a) shipping (surveys of transport vehicles and their loads) records are only kept for two years.
b) calibration records of instruments listed in paragraph VI of ANI Bulletin 80-1B are kept for only two years.
c) smear su.'veys are on a two year retention period.
d) personnel records do not have any set policy for retention.
The comments in this letter are based upon conditions, practices and property observed and information made available at the time of the inspec-tion _which was made for underwriting purposes. These comments do not purport to list all hazards nor to indicate that other hazards do not exist.
No responsibility is assumed for the correction or control of any conditions, practices or prope,rty, and neither the making of the inspection nor any report or correspondence thereon shall constitute an undertaking, on behalf of or for the benefit of the insured or others, to determine or warrant that the facilities, operations or property art safe or healthful, or are in compliance with any law, rule or regulation.
Ite Exchonf u te 245,/ 270 formincpon A.enue/ Forrmgton. Connoct<ut 06032 /(2C0677-7305 Eng. Dept.(203)677-7715/ TLub 643-029 S
1 June 26, 1981 Mr. David W. Zef f, Manager Health, Safety & Licensing Babcock & Wilcox Commercial fluclear Fuel Plant P. O. Box 800 Lynchburg, VA 24505 Page 2 81-2 It is therefore recommended that a formal policy consistent with ANI Bulletin 80-1B, including the requirement for fire-safe storagt, be established, communicated to responsible individuals in needed cognizant areas, and implemented.
in some instances where claims for radiation exposure have developed, it has been alleged thtt proper training and/or instructions as to the hazards and job related safety practices were not given. This was not discussed at the close-out meeting, but had been discussed during our specific review of your records.
81-3 It is recommended that your RWP's contain a provision for workers signatures that establishes they have read and understand the instructions.
During our tour of your facility, it was noted that the main gas shut-off valve in the pelletizing area was not posted.
81-4 It was recommended that the gas shut-of f valve be identified.
The status of the 1979 ANI recommendations is as follows:
79-1 Recommendation 79-1 requested procedures for the accurate calibration of instruments used in the determination of moisture content of the powder in the blender. Your reply of October 8,1979, stated that qualit y Control procedures provided for twice daily calibration using an NBS Standard. This adequately answers our request and 79-1 is clo. sed out.
79-2 Recommendation 79-2 requested that Training Records be signed by those attending the training session. Your October 8, 1979 response adequately stated that the forms used at training sessions to document attendance were revised to require the. signature of train-inq recipients. However, when we reviewed procedure AS-1101, "Employeg Safety Training," the exhibits did not reflect this change. This item will remain open and we will review it on our next inspection.
79-3 Recommendation 79-3 requested that a policy be established to assure the continuance of your practices of giving training to outside contractors. Your October 8,1979 letter stated that the health-safety procedure governing safety training would be modified to specify the necessary training and record retention requirements.
i Please send us a copy of this modified Health-Safety procedure.
The record retention requirements can be placed in the records reten-tion policy which we have requested in 81-2.
This item is closed out upon receipt of the revised Health-Safety procedure.
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June 26, 1981 Mr. David W. Zeff, Manager Heal th, Safety & Licensing Babcock & Wilcox Commercial Nuclear Fuel Plant P. O. Box 800 Lynchburg, VA 24505 Page 3 79-4 Recommendation 79-4 recommended that an indefinite retention period be established for RS-28 and those RS-9 special surveys associated with incident investigations. Your reply dated October 8, 1979, adequately stated that the contamination surveys for items released to unrestricted are'as will be retained indefinitely and incident investigations having a meaningful potential for future reference will be retained indefinitely. The implementation of this response will be through the establishment of a formal records retention policy as we have asked for in Recommendation 81-2.
This item is closed out.
The status of the 1980 ANI Recommendations is as follows:
80-1 Your response to 80-1, dated f;ay 13, 1980, concerning the screening of new employees for possible exposure to uranium was acceptable. We will review the implementation of this during our next inspection.
80-2 Since you have replaced the indium chip in your TLD's with a third TLD chip, this satisfied our previous request for a back-up chip.
Recommendation 80-2 is closed otit.
80-3 Your response to 80-3, dated May 13, 1980, concern'ing a provision for recording the number of the instrument on the RWP form stated that only calibrated instruments are used and that daily instrument response is checked using a check source. This satisfies our request. Rec'ommenda t ion 80-3 is closed out.
80-4 You stated adequately in your May 13, 1980 response that the event report (Monitor's log book) is included in the CNFP records retention system.
Since this dociiment will become a part of our recommendation 81-2, asking for a formal records retention policy, we will close out 80-4.
80-5 Recommendation 80-5 requested that the design of the fuel storage racks be reviewed to confirm that they will withstand the effects of any likely seismic activity. You responded to this recommendation in your letter of April 15, 1981, and it was also discussed during our visit.
It was agreed that the likelihood of accidental criticality in the event of collapse was vanishingly small.
However, the possibility
.of increased exposure to personnel still exists and the financial loss to property (fuel bundles) could be tremendous. Consequently, we believe you should continue to pursue your investigation as to the intensity of the likely earthquake for your site and an analysis of the probability and consequences of damage to the. racks and fuel in the event of maximum likely sei'mic activity.
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June 26, 1981
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' Mr. David W. Zeff, Manager Health, Safety & Licensing Babcock & Wilcox Commercial Nuclear Fuel Plant P. O. Box 800 Lynchburg, VA 24505 Page 4 80-6 Your reply to recommendation 80-6 dated December 9, 1980 stated that the criticality calculations did not need to be retained indefinitely, but that the appropriate documentation showing personnel exposure and evaluations involving those exposures did and would be retained in-definitely. This response is considered adequate. This, of course, will be implemented via your formal record retention policy which we have requested in 81-2.
This item is closed out.
Please convey our thanks to the plant staff for their cooperation.
A response to the above recommendations within the next sixty days would be appreciated.
Very truly yours,
>>>m Bruce Ernst Facility Engineer BE:me cc: Messrs.: J. Cure W. L. Arnold F. Catudal G. Weldon R. W. Newcomb F. K. Gaston
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Executive O'fices: 225 Wyman Street, Waltham. Massachuse'ts 02154 Tel: (617) 890-9300 Tetex: 92-3436 Nuclear Insurance Division October 28, 1981 x\\-
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l'<'ED Yes Mr. L. J. Hill 34 D y *.
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, Corporate Fire Protection Engineer D
.NO1/',# 'l96[/s The Babcock & Wilcox Company E' I P. O. Box 1260 tygCN3Wo. y Lynchburg, Virginia 24505 c,
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Dear Mr. Hill:
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ist The Babcock & Wilcox Company Nuclear Materials & Manufacturing Division Lynchburg, Virginia Index No. 45336.30' On behalf of MAERP, we enclose Mr. R. G. Strange's Property Reinspection Report dated September 17, 1981.
Very truly yours, John A. H. Henshaw Vi ce-P residen t JAllH/zc enCs.
cc: Messrs. Smith, Alto, Zeff 9
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Arkwright Boston Manufacturers Mu'ualInsurance Company
Arkwright-Boston Insurance Waltham Massachusetts 02154 REINSPECTION REPORT MAERP MUTUAL ATOMIC ENERGY REINSURANCE POOL FOR MCDERMOTT INCORPORATFD (THE BAECOCK & WILCOX OPERATING UNIT-NUCLEAR MATERIALS DIVISION OPERATING COMPANY INDEx 45336.30 Rte. 460 Lynchburg, Virginia 24505 sy R. G. Strange ACCOUNT 2-05000 CONFERENCE ON Sept. 17, 1981 mTH Mr. Dave Zeff; Mgr. Health Safety Licensing HOUSEKEEPING is nrly Satisfactory ARE AS SPRINKLER ED Yes
% Additional No % Needed MAINTENANCE & REPAIR is Satisfactory WATER SUPPLY is Adequate 70Lbs. Pressure SUPERVISION FIRE EQUlPMENT is Satisfactory ALL VALVES FOUND OPEN were P.E.O. & WATCHMEN is Satisfactory CRITICALITY CONTROL is Satisfactory R ADIOISOTOPE HANDLING is Satisfactory NUCLEAR REACTOR OPERATION is Satisfactory
SUMMARY
Management has excellent interest in loss prevention at this coamercial nuclear material plant.
GENERAL RDIARKS The weekly recorded inspection form has been revised to include all sprinkler
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control valves. (81-4-1)
All sprinkler control valves have been identified and tagged as to the area they control. (81-4-2)
The quantity of combustibles within the unsprinklered portion of C.N.F. Building has increased. These combustibles consist of empty fuel rods in wood crates, 6 to 8 crates in a cluster 4 ft high.
There were three separate areas of storage but not in a continuous combustible arrangement. Management will try to keep this h
storage to a minimum.
If the storage continues to increase e recommendation for z
sprinkler protection will be made.
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