1CAN118204, Forwards Addl Info Per NRC 821026 Request Re Radiation Profiles from Environ Qualifications Review.Cable Matls Capable of Withstanding Sufficient Gamma Exposure Such That Credit for Beta Shielding Can Be Taken
| ML20066F965 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/12/1982 |
| From: | John Marshall ARKANSAS POWER & LIGHT CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 1CAN118204, NUDOCS 8211190246 | |
| Download: ML20066F965 (4) | |
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U ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK ARKANSAS 72203 [501) 371-4000 November 12, 1982 1CAN118204 Director of Nuclear Reactor Regulation ATTN:
Mr. J. F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
Arkansas Nuclear One - Unit 1 Decket No. 50-313 License No. DPR-51 Environmentai Qualification -
Request for Additional Information Relating to Radiation Profiles Gentlemen:
By letter dated October 26, 1982, (1CNA108204) the NRC requested auditional information pertaining to your review of the AP&L Environmental Qualification efforts.
This letter is in response to your request.
Pertaining to your request concerning equipment not meeting the 5 x 107 radiation qualification level, we provide the following.
A review of the most recent system component evaluation work sheets (SCEW) reveals that thirty (30) items located within the ANO-1 reactor building are not qualified to the 5 x 107 rad level and were therefore chosen for specific dose reduction.
As described in section 4.1.3.1 of the attachment to our October 2, 1981, response to the SER, the inside containment dose was calculated at twenty-five selected locations.
The calculated doses ranged from approximately 3 x 106 to 5 x 107 rad; therefore, all items were 7
conservatively assigned a required valve of 5 x 10.
Upon tabulating the 30 items whose qualification did not satisfy this conservative dose, it was decided that the items would be specifically located within the containment and compared to the locations of the 25 " detector" points previously calculated.
In this way a location-specific dose was determined for each of the items.
The items are listed in Attachment I with the revised doses as indicated on their respective SCEW sheets.
The 40 year normal dose (which is considered insignificant compared to the 5 x 107 dose level) is being added to the SCEW sheets for each of the 30 devices inside containment whose radiation level had been reduced below f N thedevicedoesnotalterthequalificationstatusofanyofthe30 items.fO 7 rads.
Inclusion of the 40 year dose to the conservative level of 5 x 10 8211190246 821112 PDR ADOCK 05000313 P
PDR MEMOER MIDDLE SOUTH UTluTIES SYSTEM L
Mr. J. F. Stolz N:vimber 12, 1982 We p/ viously indicated in our October 2, 1981 response (Attachment 1 Section 4.1.3.2) to the SER why equipment other than cables is not significantly affected by beta exposure. Our position has not char.ged; nonetheless we have reviewed the SCEW sheets which list all in-containment devices at ANO-1 and based upon our knowledge of component construction, it is our contention that each of the devices has more than adequate beta shielding based on its known protective metal housing or enclosure.
In response to your statement concerning the ability of the cable jacketing material to withstand the post-accident radiation dose, we provide the following information on the three applicable cable types at ANO-1:
1.
Okonite-Okoorene jacketing and insulation (provided by Okonite Co.) is used for 600 volt power, control and instrumentation cable at ANO-1.
It has been shown by testing to be capable of withstanding a radiation dose of 2 x 108 rads (ref. SCEW sheet A-105).
2.
Bostrad 7 is used as jacketing and insulation for all BIW cable type 8374-H-002 used at ANO-1.
This cable has been tested to a level of 5.5 x 107 rads which will be indicated on the next revision of SCEW sheet A-099.
3.
The third cable type described is BIW type RG 11/U.
It consists of an outer jacket of PVC, an outer copper-braid, a layer of polyester tape, an inner copper braid, and a layer of polyethelene.
The most recent effort to qualify this cable has concluded using material analysis that the cable can withstand the maximum value of 5 x 107 rads.
It should be noted that the only known use of this cable at ANO-1 is for neutron detection instrumentation which does not require qualification.
Therefore the described cable materials used at ANO-1 are capable of withstanding sufficient gamma exposure such that credit for beta shielding can be taken as well.
Very truly yours, 12g John R. Marshall Manager, Licensing JRM:CHT:sc cc:
ATTACHMENT I' TAG #
Location Specific Dose LT-1000 3 x 108 LT-1001 1 x 10' LT-1002 3 x 108 LT-2609 3 x 108 LT-2614 3 x 108 LT-2659 1.4 x 107 LT-2664 1.4 x 107 PDT-1028 1.4 x 107 PDT-1029 1.4 x 107 PDT-1030 1.4 x 107 PDT-1031 1.4 x 107 PDT-1034 1.4 x 107 PDT-1035 1.4 x 107 PDT-1036 1.4 x 107 PDT-1037 1.4 x 107 PS-2400 8.7 x 108 PS-2401 1 x 107 i
PS-2402 1.3 x 107 PS-2403 1.4 x 107 PT-1020 1.4 x 107 PT-1021 1.4 x 107 PT-1022 1.4 x 107 PT-1023 1.4 x 107 PT-1038 1.4 x 107 PT-1039 1.4 x 107 1
TAG #
Location Specific Dose PT-1040 1.4 x 107 PT-1041 1.4 x 107 PT-2405 1.1 x 107 PT-2406 1.4 x 107 PT-2407 1.1 x 107