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| number = ML20125B319 | | number = ML20125B319 | ||
| issue date = 05/25/1976 | | issue date = 05/25/1976 | ||
| title = Forwards | | title = Forwards Pertaining to Insp Rept 50-263/76-05 & Request That Licensee Provide Info Re Meteorological Data Per TS 6.7.A.2.h(2) | ||
| author name = Allan J | | author name = Allan J | ||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | ||
Line 11: | Line 11: | ||
| contact person = | | contact person = | ||
| document report number = NUDOCS 9212090307 | | document report number = NUDOCS 9212090307 | ||
| title reference date = 04-27-1976 | |||
| package number = ML20125B294 | | package number = ML20125B294 | ||
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE | | document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE | ||
Line 18: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:- _ _ - - - - - | ||
_ _ . . | |||
w- | |||
- | |||
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e | |||
, | |||
4' | |||
UNITED STATES | |||
NUCLEAR REGUL ATORY COMMISSION | |||
f REolONlli | |||
199 Roo&EVELT RO AD | |||
OLEN ELLYN, ILLINot$ 60137 | |||
May 25, 3976 | |||
L. B. Higginbotham, Chief, Safety and Environmental Programs Branch | |||
Office of Inspection and Enforcement, lleadquarters | |||
NORTHERN STATES POWER COMPANY (MONTICELLO) | |||
DOCKET NO. 50-263 | |||
(AITS NO. F30178110) | |||
Attached is a copy of a letter dated April 27, 1976, from L. O. Mayer, | |||
Manager of Nuclear Support Services, Northern States Power Company, | |||
pertaining to the IE Inspection Report No. 050-263/76-05. Two points | |||
on the meteorological program and elevated radioiodine levels raised | |||
in the NSP letter in response to our inspection report were brought | |||
to your attention in a acparate memo dated April 28, 1976, for | |||
action (AITS F30178HO, revised completion date 6-10-76). Our memo | |||
was sent to you prior to our receipt of the NSP letter. We would | |||
appreciate receiving a prompt response to this AITS item so we can | |||
prepare a followup response with the IE position to the items | |||
addressed in the NSP letter. In accordance with the above, please | |||
provide an interpretation of Technical Specification 6.7.A.2.h(2) when , | |||
the concentration levels in various environmental media indicate the | |||
likelihood of public intakes in excess of 1% of those that could | |||
result from continuous exposure to the concentration values listed | |||
in Appendix B, Ta~leo II, Part 20. | |||
We alsn understand that interim Technical Specifications on Section- | |||
2.4 Radioactive Ef fluents and Section 4.8 Radiologici i Environmental | |||
Monitoring Program are being prepared. Our commente on the proposed | |||
T/S change request of October 15, 1975, and March 1, 1976, were | |||
also sent to you on April 28, 1976. We believe it is necessary to | |||
include a T/S change in the plant reporting requirements to clarify | |||
the intent of Technical Specification 6.7.A.2.h(2). | |||
Plcase provide guidance on how we can obtain information such as | |||
meteorological data from the licensee in accordance with Regulatory | |||
Guides 121 and 4.8 when such data are not renuired in the Technical | |||
Specifications. | |||
N | |||
( : CM GM ) | |||
w y-b James M. Allan, Chief | |||
9212090307 760601 Fuel Facility and Materials | |||
PDR ADOCK 05000263 i | |||
G PDR Safety Branch | |||
Attachment: | |||
As stated | |||
cc w/ attachment: | |||
L. Cohen, IE:HQ | |||
.. | |||
-,,, _.,_ ~ - | |||
. ., | |||
~ | |||
y. | |||
, .1% !i:I.d. a: - | |||
., .. | |||
, | |||
. | |||
, | |||
' * | |||
a j ' | |||
N O' It T l t C it e 4 S T A T ti S P o W C tt COMPANY | |||
. | |||
.. . | |||
, | |||
unmeAe.ot.i[i.emunooTAoe4ot | |||
. . | |||
April 27, 1976 | |||
Mr James M Allan, Chief | |||
Fuel Facility and Materials Safety Branch | |||
Office of Inspection & Enforcement, Region III | |||
U S Nuclear Regulator'y Commission * | |||
799 Roosevelt Road | |||
G1en Ellyn, IL 60137 | |||
Dear Mr Allan: | |||
MONTICELLO NUCLEAR GENERATING pud 1T | |||
Docke t No. 50-263 License No. DPR-22 | |||
Your letter dated April 8,19/6, which was roccived on April 9,1976, transmitted | |||
IE Inspection Report No. 050-263/76-05. 'The Inspection Report states at two | |||
points that certain items of discussion will be referred to the Office of Nuclear | |||
Reactor Regulation and will be ny amined at subsequent inspections. *1his letter is | |||
written to provide clarificati nr the record of the NSp position on those. | |||
matters and several other topic- iscussed with the NRC personnci during their | |||
inspection. Our con:nents will reference the Inspection Report by page number and | |||
paragraph designation. | |||
Panc 2, paranraph A and pane 12, paronraph h | |||
' | |||
NSP took the position that there are no regulatory requirements or Technical | |||
Specifications covering the Monticello plant which require the submission of | |||
meteorological data. We further pointed out that the NRC Regulatory Guides are | |||
not requirements. The discuccion that ensued from that point on uas with respect | |||
to the recommandations contained in Regulatory Guides 4.8 and ' .21 for inclusion | |||
with the semiannual effluents report of meteorological data and dose computations. | |||
We have reviewed the impact of a reporting requirement of this nature and find | |||
that a considerabic initial investment in manpcuer, ccxuputer programs, consultant | |||
help and equipment would be required to provide this type of data. In addition, it | |||
would require a continuing manpcuer requirement, beyond that which we currently | |||
have avai1M 'e, and possibly intermittent or continuous consultant help to provide | |||
the data that the NRC proposes to be submitted each six months. | |||
We carried the discussion further with the observation that the NRC is supplied | |||
wi th site meteorology which is used in a conservative manner with plant effluent | |||
infonnation t o set regulatory limits on radioactive effluents from the plant and | |||
highly conservative design objectives. 'lhis is coupled with requirements for an | |||
ext.cnuive Radiation Environmental Monitoring program to confirm that the limits | |||
l and design objectives have been set at such a 1cyc1 that there are no unexpected | |||
l cffects on the er.vironment from radioactive offinent releases from the plant. We | |||
L | |||
made the concluding observation that the nemlannual subminsion of meteorological | |||
! data and dose calculations would appear to be more of a data collection ef fort | |||
l | |||
. | |||
hS- M7 ~~b , | |||
y | |||
. | |||
. | |||
.- | |||
* | |||
. NORTHIIRN GTATES POWER COMPANY | |||
- ,- | |||
., . | |||
-( ' | |||
' | |||
- | |||
, | |||
' . | |||
, ,. . , - | |||
'. | |||
* | |||
Mr James !! Allan | |||
Page 2 | |||
April 27,1976 | |||
than information that is needed for the assessment of safety related activitics | |||
and that the manpuser and equipment expenditures that would be involved appear to | |||
be unwarranted. | |||
Several years ago NSP began work on a research project for providing transmission | |||
of meteorological and of fluent data from NSP's fossil and nucicar plants to a | |||
centralized computcr-oriented data collection system. A prototype " digitizing | |||
transmitter" vas built, t ested, and installed at the !!onticello plant on the | |||
meteorolegical tuser about nine months ago. The " digitizing transmitter" operation | |||
has been reasonably successful for the purpose intended, but it has not been It was | |||
suit abic for use for submittals to the NRC, such as Appendix I compliance. | |||
also intended that a teletypewriter would be provided in the Monticello control | |||
room to provide supplemental recording of the " digitizing transmitter" information. | |||
It should be noted that the Monticello control room aircady has a wind direction | |||
and velocity recorder in operation. Since the teletypcuriter system is based | |||
, | |||
on use of the prototype device, which might be replaced with more suitabic equip- | |||
ment, it has been decided not to install this supplemental equipment in the | |||
Monticello control room. Meteorological data continues to be obtained from the | |||
, | |||
300' tower in strip chart form and is retained in accordance with recordkceping | |||
requirements. | |||
Paragraph h on page 12 reference a computer printout as being availabic, but not | |||
in use. This is information frcu the prototype " digitizing transmitter" equipment | |||
and is not in a format or of the ;uality which could be put to beneficial use by | |||
the nuclear plant. It should also be noted that the licensec is currently hand | |||
reducing data from the metaorological strip charts in order to obtain a full year | |||
, | |||
j | |||
of acceptabic quality meteorological data in connection with the Appendix I | |||
compliance submittal. This infomation will update the meteorological data that | |||
' | |||
has been provided to the NRC in earlier submittals. | |||
, | |||
; | |||
_ Pane 6_, paranraph 3.a | |||
, | |||
Since the Monticello plant does not have Appendix B Technical Specifications, the | |||
conuncut in regard to ECAD maintaining cognizance of aquatic biota protection con- | |||
ditions, reporting to NSS when protection conditions are exceeded, etc. , is not | |||
, | |||
' | |||
applicabic to the Monticello plant at the present time. | |||
+ The NSS Department .does not have administrative responsibility for non-radiological | |||
sampling as mentioned in the second sub-paragraph. The !!SS responsibiliLy for a | |||
, | |||
reductiod and computer processing of the meteorological program results is not | |||
routine responsibility but resulted f rom the needs for obtaining this information | |||
on a one-time basis for the Appendix I cuepliance submi.ttal. The tiSS Department | |||
has not initiated development of calculational procedures for donc pathway report- | |||
ing to the NRC in line with discussion in an earlier paragraph that there are no | |||
requirements for this at Monticello. | |||
. | |||
F | |||
. | |||
. | |||
, - . | |||
..Th | |||
~ ' | |||
** | |||
NORTHERN GTATCO POWER COMPANY , | |||
.. | |||
. | |||
. , , . | |||
, | |||
Mr Jame; M Allan | |||
Page 3 | |||
April 27, 1976 | |||
Panc 7. parnnraph c . | |||
We are not aware of any computerized system used by-the NSS Department for report- | |||
ing the results of program audits and inspections to supervision and nanagement for | |||
their review. | |||
Panc 8, paranraph 5 , | |||
A revised Radiation Environmental Moultoring Program was submitted to the Ccmmission | |||
on October 15, 1975 as a license amendment request; the program has not yet been | |||
put into effect since the licenso amendment has not been issued by the NRC. The | |||
March 1, 1976 submittal referenced in the inspection report involves interim | |||
Technical Specifications on radioactive effluents; the Radiation Environmental | |||
Monitoring Technical Specification pages that were included uith the liarch 1,1976 | |||
submittal were included only because there are changes in pagination in this section | |||
due to the removal of radioactive effluents from Appendix A and their transfer to | |||
Appendix E. . | |||
Pancs 9-11, paranraph d | |||
The inspection report correctly reficcts the increases in icvels of I-131 in milk | |||
during the summer of 1975; hauever, it does not point out that these Icvnis have | |||
been greatly reduced since replacement of the defective initial 7x7 fuel during | |||
the refueling outage in October, 1975. | |||
On the bottom of page 10 and the top of page 11, still under parsgraph d, there is | |||
a discussion of the number of iodine sampics which should be included in the | |||
averaging to determine if additional repprting is required on estimates of likely | |||
exposurcs to individuals and population groups. The Technical Specification re- | |||
quirement for supplemental reporting is based en the likelihood of intakes in . | |||
execca of 17. of thosc that could result from continuous exposures to the concen- | |||
tration values of Appendix B, Tabic II, Part 20. This appears to be similar to | |||
design objective reporting. It is our position that the sampics should be | |||
averaged over a calendar quarter and if the average concentrations of I-131 in | |||
milk are greater than 2.4pci/1, then the supplemental information would be required. | |||
Yours very truly, | |||
c Y O. A " | |||
r . | |||
L O 11ayer, PE | |||
Manager of Nuclear Support Services | |||
. | |||
LOM/ak | |||
. | |||
cc: Victor Stc11o | |||
G Charnoff | |||
HPCA - Attu: J W Pennan | |||
. | |||
. | |||
. l | |||
. | |||
_. _ _ _ _ _ . _ _ _ | |||
. . _ _ _ _ __ __ , | |||
w . - -- - - - | |||
I | |||
. . | |||
s- | |||
' | |||
* * UNITtD $T ATES | |||
, | |||
NUCLEAR HUGULATORY COMMISSION | |||
nroloN 11 | |||
799 floo5tVELT flo Ao | |||
GLEN ELLYN, ILLlHolt C0137 | |||
May 25, 1976 | |||
L. B. Iligginbotham, Chief, Safety and_ Environmental Programs Branch | |||
Of fice of Inspection and Enforcement, !!cadquarters | |||
NORTilERN STATES POWER COMPANY (MONTICELLO) | |||
DOCKET NO. 50-263 | |||
(AITS NO. F30378HO) | |||
Attached is a copy of a Ictter dated April 27, 1976, from L. O. Mayer, | |||
Manager of Nuclear Support Services Northern States Power Company, | |||
pertaining to the IE Inspection Report No. 050-263/76-05. Two points | |||
- on the meteorological program and c]cvated radiciodine levels raised | |||
in the NSP 1ctter in response to our inspection report were brought | |||
to your attention in a separate memo dated April 28, 1976, for | |||
action (AITS F30178HO, revised completion date 6-10-76). Our memo | |||
was sent to you prior to our receipt of the NSP letter. We would | |||
appreciate rocciving a prompt response to this AITS iten so we can | |||
prepare a followup response with the IE position to the items | |||
addressed in the NSP letter. In accordance with the above, please | |||
provide an interpretation of Technical Specification 6.7.A.2.h(2) when | |||
the concentration IcVels in various environmental media indicate the | |||
likelihood of public intakes in excess of 1% of those that could | |||
result from continuous exposure to the concent ration values listed | |||
'in Appendix B, Table 11. Part 20. | |||
We also understand that interi, Technical Specifications on Section | |||
2.4 Radioactive Effluents and Section 4.8 Radiological Environmental | |||
Monitoring Program are being prepared. Our comments on the proposed . | |||
T/S change request of October 15, 1975, and March 1, 1976, were | |||
also sent to you on April 28, 1976. We believe it is necessary to | |||
include a T/S change in the plant reporting requirements to clarify | |||
the intent of Technical Specification 6.7.A.2.h(2). | |||
Picase. provide guidance on how we can obtain information such as | |||
meteorological data from the licensce in accordance with Regulatory | |||
Guides L 21 and 4.8 when such data are not required in the Technical | |||
Specificatiqns. | |||
NY | |||
, QW ** h i p. t t a V | |||
- g g -James M. Allan, Chief | |||
( Fuel Facility and Materials | |||
Safety Branch | |||
Attachment: | |||
As stated | |||
cc w/ attachment: | |||
L. Cohen. IE:HO . | |||
p g nR'OY, . | |||
( | |||
, | |||
; | |||
f * | |||
. | |||
* ~ '' | |||
* _ | |||
- | |||
,. | |||
.-' | |||
. | |||
, . , | |||
> | |||
_. . - . | |||
. . | |||
* | |||
N O H T_ H E n .4- _GTATCS PoWtn COMPANY | |||
, | |||
.. ., siwucanew usuwu oora no4ei | |||
, | |||
. . | |||
April 27,1976 -. | |||
. | |||
Mr Jancs M Allan, Chief | |||
Puc1 Facility and Materials Safety L.anch | |||
Office of Inspection.6 Enforcement, Region III | |||
U S_ Nuclear Regulator'y Ccanission ' | |||
799 noosevcit Road | |||
Clon Ellyn, IL 60137 | |||
Dear Mr Allan: . | |||
MONTICELLO HUCLEAR GENERATING Pud 4T | |||
Docket No. 50-263 License No. DPR-22 | |||
Your letter dated April .8,1976, which was rFccived on April 9,1976, transmitted | |||
-IE Inspection Report No. 050-263/76-05. The Inspection Report states at tuo | |||
points that certain items of. discussion will be referred to the Office of Nuclear | |||
Reactor Regulation.and will be examined at subecquent inspections. '1his letter is - | |||
written to provide clarification for the record of the USP position on those | |||
matters and ccveral other topics discussed uith the NRC personnel during their | |||
i nspec tion.- Our coments will reference the Inspection Report-by page_ number and | |||
paragraph designation. | |||
Pane 2, paranraph A and pano 12. paranraph h | |||
NSP took the position that: there arc _no- regulatory requirements or Technical | |||
. Specifications covering the Monticello plant which. require the submission of | |||
matcorological data. - We further pointed out that the URC Regulatory Guides are - | |||
not requirements. The discussion that ensued from. that point -on was with respect | |||
' | |||
to the reconmendations contained in Regulatory Guides 4.8 and -1.21 for inclusion | |||
_ with the-semiannual effluents report 'of meteorological data and dosc computations. | |||
;- ' We have ' revicued the impact of a . reporting requirement of this = nature and - find - | |||
that a:considerabic initini investment in manpcuer, computer programs, _ consultant | |||
hcip and equipment would be required to provide this~ type of dhta. In addition,';it | |||
, would ' require a continuing' manpower requirement, heyond that i hich we currently | |||
, | |||
have availulle, and possibly1 intermittent or continuous consultant help to provide | |||
l the data that the NRC, proposes to be submitted each six months. | |||
We carried - the discussion further with the observation that the NRC is supplied | |||
- | |||
with site meteorology which is used in a conservative manner with plant ef fluent . | |||
information Lo set regulatory limits- on radioactivo efflucnts from the plant and | |||
' highly conservative design objectives. '1his is c_oupled with- requirements for an | |||
' | |||
extensive Radiation-Environmental Monitoring Program to confirm that the limits | |||
4- | |||
4' | |||
and design _ objectives have been set at such a Icyc1 that there are no unexpected | |||
cffects on the environment from radioactive affluent relcases from the. plant. - Uc | |||
made the concluding ohnervation. that t he semiamnial submission of meteorological. | |||
! data nnd donc calculations would appear to be more-of n' data collection ef fort | |||
. | |||
. | |||
, | |||
... | |||
- W r | |||
Jt) @ 4:o4 0 9 | |||
*--,.,r - , , , - .4.--, 3-n | |||
M' : - | |||
. | |||
- | |||
;., | |||
NORTHERN GTATEG POWCrf COMPANY . | |||
* * , %' | |||
. | |||
- < | |||
... | |||
. | |||
. | |||
. | |||
* | |||
3 . | |||
. | |||
ifr Jannes ti Allan | |||
Panc 2 | |||
April 27,1976 | |||
than information that is necded for the assessment of safety related octivitics | |||
and that the manpwer and equipment expenditures that would be involved appear to | |||
be unwarranted. | |||
Several years ago NSP began work on a research project for providing transmission | |||
of matcorological and of fluent data from 11SP's for: and nucicar plants to a | |||
centralized computer-oriented data collection system. A prototype " digitizing | |||
transmitter" vas built, t ested, and installed at the 11onticc110 plant on the | |||
meteorological twer about nine months ago. %c " digitizing transmitter" operation | |||
has been reasonably successful for the purpose intended, but it has not been It was | |||
suitabic for use for submittals to the NRC, such as Appendix I compliance. | |||
also intended that a teletypewriter vould he provided in the Monticello control | |||
room to provide supplemental recording of the " digitizing transmitter" information. | |||
It should be noted that the Monticello control room circady has a wind dircetion | |||
and velocity recorder in operation. Since the teletypcuriter system is based | |||
on use of the prototype device, which might be replaced with more suitabic equip- | |||
ment, it has been decided not to install this supplemental equipment in the | |||
Monticello control room. Met corological data continues to be obtained f rcnr. the | |||
300' tower in strip chart form and is retained in accordance with recordkeeping | |||
r equi r eane nt s . | |||
Paragraph h on page 12 reference a ccmputer printout as being availabic, but not | |||
in use. This is information fro the prototype "digitining transmitter" equipment | |||
and is not in a format or of the juality which could be put to beneficial use by | |||
the nuclear plant. It should also be noted that the licensec is currently hand | |||
reducing data from the meteorological strip charts in order to obtain a full year | |||
of acceptabic quality meteorological data in connection with the Appendix I | |||
compliance submittal. This information will update the meteorological data that | |||
' | |||
, has been provided to the NRC in earlier submittals. . | |||
l _P_ age 6, paranraph 3. a , | |||
i Since the Monticello plant does not have Appendix D Technical Specifications, the | |||
; connent in regard to EGAD maintaining cognizance of aquatic biota protection con- | |||
' | |||
ditions, reporting to NSS when protection conditions are exceeded, etc., is not | |||
applicabic to the Monticello plant at the present time, | |||
e The NSS Department <loca not have administrative responsibility f or non-radiological | |||
sampling as mentioned in the second sub-paragraph. The NSS responsibility for | |||
reduc t ioti and cunputer processing of the untcorological program results is not a | |||
. | |||
routine renponnihility but resnited from the needs for obtaining this information | |||
on a one-time basis for the Appendix 1 compliance submittal. The NSS Department | |||
has not initiated development of calculational procedures for donc pathway report- | |||
ing to the NRC in line with dircussion in an earlier paragraph that there are no | |||
requirements for this at Monticello. | |||
l | |||
' | |||
. | |||
! | |||
I | |||
t | |||
e | |||
-_ _ | |||
.* NORTHERN OTATED POWER COM18ANY | |||
_ | |||
. . . s | |||
* . | |||
. . . , | |||
, | |||
' | |||
. | |||
. | |||
, | |||
fir James !! Atlan | |||
Page 3 . | |||
4 | |||
April 27.1970 | |||
Panc 7. onranraph c_* . | |||
We are not aware of any computerized system used by the NSS Department for report- | |||
ing the renults of program audits and inspections to supervision and manage;nent for | |||
their review. | |||
Panc 8, parnnraph 5 | |||
A revircd Radiation Environmental !!onitoring Program uns submitted to the Commission | |||
< | |||
on October 15, 1975 as a license amendment request; the program hoc not yet been | |||
put into ef fect since the license amendment has not been issued by the !!nc. The | |||
. March 1, 1976 submittal referenced in the inspection report involves interim | |||
Technical Specifications on radioactive ef fluents; the nadiation F.nvironmental | |||
Monitoring Technical Specification pages that were included with the !! arch 1,1976 | |||
cubmittal ucre included only because there are changes in pagination in this section | |||
due to the removal of radioactive offluents from Appent _x A and their transfer to | |||
Appendix B. | |||
Pancs 9-11, paranraph d | |||
' | |||
The inspection report correctly reficcts the increases in Icvels of I-131 in milk | |||
during the summer of 1975; however, it does not point out that these Icvels have | |||
. been greatly reduced since replacement of the defective initial 7x7 fuel during | |||
the refueling outage in October, 1975. | |||
; | |||
On the bottom of page 10 and the top of page 11, still under paragraph d, there is | |||
a discussion of the number of iodine sampics which should be included in the | |||
averaging to determine if additional reporting is required on estimates of likely | |||
exposures to individuals and population groups. The Technical Specification re- | |||
quirement for supplemental reporting is based on the likelihood of intahes in | |||
excess of 17. of thosc that could result from continuous exposures to the concon- | |||
tration values of Appendix B, Tabic II, Part 20. This appears to be similar to | |||
design objective reporting. It is our position that the sampics should be | |||
averaged over a calendar quarter and if the average concentrations of I-131 in | |||
milk are greater than 2.4pci/1, then the supplementn1 information would be required. | |||
Yours very truly, | |||
b. & ff | |||
' | |||
L O Mayor, PE | |||
Manager of Nuclear Support Scryices | |||
. | |||
1DM/ak | |||
. | |||
cc: Victor Stello | |||
C Charnorf | |||
MPCA - Attu: J W Ferman | |||
* | |||
. | |||
e | |||
4 # e | |||
}} | }} |
Latest revision as of 22:37, 22 September 2022
ML20125B319 | |
Person / Time | |
---|---|
Site: | Monticello |
Issue date: | 05/25/1976 |
From: | Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
To: | Higginbotham L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
Shared Package | |
ML20125B294 | List: |
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See also: IR 05000263/1976005
Text
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UNITED STATES
NUCLEAR REGUL ATORY COMMISSION
f REolONlli
OLEN ELLYN, ILLINot$ 60137
May 25, 3976
L. B. Higginbotham, Chief, Safety and Environmental Programs Branch
Office of Inspection and Enforcement, lleadquarters
NORTHERN STATES POWER COMPANY (MONTICELLO)
DOCKET NO. 50-263
(AITS NO. F30178110)
Attached is a copy of a letter dated April 27, 1976, from L. O. Mayer,
Manager of Nuclear Support Services, Northern States Power Company,
pertaining to the IE Inspection Report No. 050-263/76-05. Two points
on the meteorological program and elevated radioiodine levels raised
in the NSP letter in response to our inspection report were brought
to your attention in a acparate memo dated April 28, 1976, for
action (AITS F30178HO, revised completion date 6-10-76). Our memo
was sent to you prior to our receipt of the NSP letter. We would
appreciate receiving a prompt response to this AITS item so we can
prepare a followup response with the IE position to the items
addressed in the NSP letter. In accordance with the above, please
provide an interpretation of Technical Specification 6.7.A.2.h(2) when ,
the concentration levels in various environmental media indicate the
likelihood of public intakes in excess of 1% of those that could
result from continuous exposure to the concentration values listed
in Appendix B, Ta~leo II, Part 20.
We alsn understand that interim Technical Specifications on Section-
2.4 Radioactive Ef fluents and Section 4.8 Radiologici i Environmental
Monitoring Program are being prepared. Our commente on the proposed
T/S change request of October 15, 1975, and March 1, 1976, were
also sent to you on April 28, 1976. We believe it is necessary to
include a T/S change in the plant reporting requirements to clarify
the intent of Technical Specification 6.7.A.2.h(2).
Plcase provide guidance on how we can obtain information such as
meteorological data from the licensee in accordance with Regulatory
Guides 121 and 4.8 when such data are not renuired in the Technical
Specifications.
N
( : CM GM )
w y-b James M. Allan, Chief
9212090307 760601 Fuel Facility and Materials
PDR ADOCK 05000263 i
G PDR Safety Branch
Attachment:
As stated
cc w/ attachment:
L. Cohen, IE:HQ
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N O' It T l t C it e 4 S T A T ti S P o W C tt COMPANY
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unmeAe.ot.i[i.emunooTAoe4ot
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April 27, 1976
Mr James M Allan, Chief
Fuel Facility and Materials Safety Branch
Office of Inspection & Enforcement, Region III
U S Nuclear Regulator'y Commission *
799 Roosevelt Road
G1en Ellyn, IL 60137
Dear Mr Allan:
MONTICELLO NUCLEAR GENERATING pud 1T
Docke t No. 50-263 License No. DPR-22
Your letter dated April 8,19/6, which was roccived on April 9,1976, transmitted
IE Inspection Report No. 050-263/76-05. 'The Inspection Report states at two
points that certain items of discussion will be referred to the Office of Nuclear
Reactor Regulation and will be ny amined at subsequent inspections. *1his letter is
written to provide clarificati nr the record of the NSp position on those.
matters and several other topic- iscussed with the NRC personnci during their
inspection. Our con:nents will reference the Inspection Report by page number and
paragraph designation.
Panc 2, paranraph A and pane 12, paronraph h
'
NSP took the position that there are no regulatory requirements or Technical
Specifications covering the Monticello plant which require the submission of
meteorological data. We further pointed out that the NRC Regulatory Guides are
not requirements. The discuccion that ensued from that point on uas with respect
to the recommandations contained in Regulatory Guides 4.8 and ' .21 for inclusion
with the semiannual effluents report of meteorological data and dose computations.
We have reviewed the impact of a reporting requirement of this nature and find
that a considerabic initial investment in manpcuer, ccxuputer programs, consultant
help and equipment would be required to provide this type of data. In addition, it
would require a continuing manpcuer requirement, beyond that which we currently
have avai1M 'e, and possibly intermittent or continuous consultant help to provide
the data that the NRC proposes to be submitted each six months.
We carried the discussion further with the observation that the NRC is supplied
wi th site meteorology which is used in a conservative manner with plant effluent
infonnation t o set regulatory limits on radioactive effluents from the plant and
highly conservative design objectives. 'lhis is coupled with requirements for an
ext.cnuive Radiation Environmental Monitoring program to confirm that the limits
l and design objectives have been set at such a 1cyc1 that there are no unexpected
l cffects on the er.vironment from radioactive offinent releases from the plant. We
L
made the concluding observation that the nemlannual subminsion of meteorological
! data and dose calculations would appear to be more of a data collection ef fort
l
.
hS- M7 ~~b ,
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. NORTHIIRN GTATES POWER COMPANY
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Mr James !! Allan
Page 2
April 27,1976
than information that is needed for the assessment of safety related activitics
and that the manpuser and equipment expenditures that would be involved appear to
be unwarranted.
Several years ago NSP began work on a research project for providing transmission
of meteorological and of fluent data from NSP's fossil and nucicar plants to a
centralized computcr-oriented data collection system. A prototype " digitizing
transmitter" vas built, t ested, and installed at the !!onticello plant on the
meteorolegical tuser about nine months ago. The " digitizing transmitter" operation
has been reasonably successful for the purpose intended, but it has not been It was
suit abic for use for submittals to the NRC, such as Appendix I compliance.
also intended that a teletypewriter would be provided in the Monticello control
room to provide supplemental recording of the " digitizing transmitter" information.
It should be noted that the Monticello control room aircady has a wind direction
and velocity recorder in operation. Since the teletypcuriter system is based
,
on use of the prototype device, which might be replaced with more suitabic equip-
ment, it has been decided not to install this supplemental equipment in the
Monticello control room. Meteorological data continues to be obtained from the
,
300' tower in strip chart form and is retained in accordance with recordkceping
requirements.
Paragraph h on page 12 reference a computer printout as being availabic, but not
in use. This is information frcu the prototype " digitizing transmitter" equipment
and is not in a format or of the ;uality which could be put to beneficial use by
the nuclear plant. It should also be noted that the licensec is currently hand
reducing data from the metaorological strip charts in order to obtain a full year
,
j
of acceptabic quality meteorological data in connection with the Appendix I
compliance submittal. This infomation will update the meteorological data that
'
has been provided to the NRC in earlier submittals.
,
_ Pane 6_, paranraph 3.a
,
Since the Monticello plant does not have Appendix B Technical Specifications, the
conuncut in regard to ECAD maintaining cognizance of aquatic biota protection con-
ditions, reporting to NSS when protection conditions are exceeded, etc. , is not
,
'
applicabic to the Monticello plant at the present time.
+ The NSS Department .does not have administrative responsibility for non-radiological
sampling as mentioned in the second sub-paragraph. The !!SS responsibiliLy for a
,
reductiod and computer processing of the meteorological program results is not
routine responsibility but resulted f rom the needs for obtaining this information
on a one-time basis for the Appendix I cuepliance submi.ttal. The tiSS Department
has not initiated development of calculational procedures for donc pathway report-
ing to the NRC in line with discussion in an earlier paragraph that there are no
requirements for this at Monticello.
.
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NORTHERN GTATCO POWER COMPANY ,
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Mr Jame; M Allan
Page 3
April 27, 1976
Panc 7. parnnraph c .
We are not aware of any computerized system used by-the NSS Department for report-
ing the results of program audits and inspections to supervision and nanagement for
their review.
Panc 8, paranraph 5 ,
A revised Radiation Environmental Moultoring Program was submitted to the Ccmmission
on October 15, 1975 as a license amendment request; the program has not yet been
put into effect since the licenso amendment has not been issued by the NRC. The
March 1, 1976 submittal referenced in the inspection report involves interim
Technical Specifications on radioactive effluents; the Radiation Environmental
Monitoring Technical Specification pages that were included uith the liarch 1,1976
submittal were included only because there are changes in pagination in this section
due to the removal of radioactive effluents from Appendix A and their transfer to
Appendix E. .
Pancs 9-11, paranraph d
The inspection report correctly reficcts the increases in icvels of I-131 in milk
during the summer of 1975; hauever, it does not point out that these Icvnis have
been greatly reduced since replacement of the defective initial 7x7 fuel during
the refueling outage in October, 1975.
On the bottom of page 10 and the top of page 11, still under parsgraph d, there is
a discussion of the number of iodine sampics which should be included in the
averaging to determine if additional repprting is required on estimates of likely
exposurcs to individuals and population groups. The Technical Specification re-
quirement for supplemental reporting is based en the likelihood of intakes in .
execca of 17. of thosc that could result from continuous exposures to the concen-
tration values of Appendix B, Tabic II, Part 20. This appears to be similar to
design objective reporting. It is our position that the sampics should be
averaged over a calendar quarter and if the average concentrations of I-131 in
milk are greater than 2.4pci/1, then the supplemental information would be required.
Yours very truly,
c Y O. A "
r .
L O 11ayer, PE
Manager of Nuclear Support Services
.
LOM/ak
.
cc: Victor Stc11o
G Charnoff
HPCA - Attu: J W Pennan
.
.
. l
.
_. _ _ _ _ _ . _ _ _
. . _ _ _ _ __ __ ,
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- * UNITtD $T ATES
,
NUCLEAR HUGULATORY COMMISSION
nroloN 11
799 floo5tVELT flo Ao
GLEN ELLYN, ILLlHolt C0137
May 25, 1976
L. B. Iligginbotham, Chief, Safety and_ Environmental Programs Branch
Of fice of Inspection and Enforcement, !!cadquarters
NORTilERN STATES POWER COMPANY (MONTICELLO)
DOCKET NO. 50-263
(AITS NO. F30378HO)
Attached is a copy of a Ictter dated April 27, 1976, from L. O. Mayer,
Manager of Nuclear Support Services Northern States Power Company,
pertaining to the IE Inspection Report No. 050-263/76-05. Two points
- on the meteorological program and c]cvated radiciodine levels raised
in the NSP 1ctter in response to our inspection report were brought
to your attention in a separate memo dated April 28, 1976, for
action (AITS F30178HO, revised completion date 6-10-76). Our memo
was sent to you prior to our receipt of the NSP letter. We would
appreciate rocciving a prompt response to this AITS iten so we can
prepare a followup response with the IE position to the items
addressed in the NSP letter. In accordance with the above, please
provide an interpretation of Technical Specification 6.7.A.2.h(2) when
the concentration IcVels in various environmental media indicate the
likelihood of public intakes in excess of 1% of those that could
result from continuous exposure to the concent ration values listed
'in Appendix B, Table 11. Part 20.
We also understand that interi, Technical Specifications on Section
2.4 Radioactive Effluents and Section 4.8 Radiological Environmental
Monitoring Program are being prepared. Our comments on the proposed .
T/S change request of October 15, 1975, and March 1, 1976, were
also sent to you on April 28, 1976. We believe it is necessary to
include a T/S change in the plant reporting requirements to clarify
the intent of Technical Specification 6.7.A.2.h(2).
Picase. provide guidance on how we can obtain information such as
meteorological data from the licensce in accordance with Regulatory
Guides L 21 and 4.8 when such data are not required in the Technical
Specificatiqns.
NY
, QW ** h i p. t t a V
- g g -James M. Allan, Chief
( Fuel Facility and Materials
Safety Branch
Attachment:
As stated
cc w/ attachment:
L. Cohen. IE:HO .
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N O H T_ H E n .4- _GTATCS PoWtn COMPANY
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April 27,1976 -.
.
Mr Jancs M Allan, Chief
Puc1 Facility and Materials Safety L.anch
Office of Inspection.6 Enforcement, Region III
U S_ Nuclear Regulator'y Ccanission '
799 noosevcit Road
Clon Ellyn, IL 60137
Dear Mr Allan: .
MONTICELLO HUCLEAR GENERATING Pud 4T
Docket No. 50-263 License No. DPR-22
Your letter dated April .8,1976, which was rFccived on April 9,1976, transmitted
-IE Inspection Report No. 050-263/76-05. The Inspection Report states at tuo
points that certain items of. discussion will be referred to the Office of Nuclear
Reactor Regulation.and will be examined at subecquent inspections. '1his letter is -
written to provide clarification for the record of the USP position on those
matters and ccveral other topics discussed uith the NRC personnel during their
i nspec tion.- Our coments will reference the Inspection Report-by page_ number and
paragraph designation.
Pane 2, paranraph A and pano 12. paranraph h
NSP took the position that: there arc _no- regulatory requirements or Technical
. Specifications covering the Monticello plant which. require the submission of
matcorological data. - We further pointed out that the URC Regulatory Guides are -
not requirements. The discussion that ensued from. that point -on was with respect
'
to the reconmendations contained in Regulatory Guides 4.8 and -1.21 for inclusion
_ with the-semiannual effluents report 'of meteorological data and dosc computations.
- - ' We have ' revicued the impact of a . reporting requirement of this = nature and - find -
that a:considerabic initini investment in manpcuer, computer programs, _ consultant
hcip and equipment would be required to provide this~ type of dhta. In addition,';it
, would ' require a continuing' manpower requirement, heyond that i hich we currently
,
have availulle, and possibly1 intermittent or continuous consultant help to provide
l the data that the NRC, proposes to be submitted each six months.
We carried - the discussion further with the observation that the NRC is supplied
-
with site meteorology which is used in a conservative manner with plant ef fluent .
information Lo set regulatory limits- on radioactivo efflucnts from the plant and
' highly conservative design objectives. '1his is c_oupled with- requirements for an
'
extensive Radiation-Environmental Monitoring Program to confirm that the limits
4-
4'
and design _ objectives have been set at such a Icyc1 that there are no unexpected
cffects on the environment from radioactive affluent relcases from the. plant. - Uc
made the concluding ohnervation. that t he semiamnial submission of meteorological.
! data nnd donc calculations would appear to be more-of n' data collection ef fort
.
.
,
...
- W r
Jt) @ 4:o4 0 9
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.
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NORTHERN GTATEG POWCrf COMPANY .
- * , %'
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.
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.
ifr Jannes ti Allan
Panc 2
April 27,1976
than information that is necded for the assessment of safety related octivitics
and that the manpwer and equipment expenditures that would be involved appear to
be unwarranted.
Several years ago NSP began work on a research project for providing transmission
of matcorological and of fluent data from 11SP's for: and nucicar plants to a
centralized computer-oriented data collection system. A prototype " digitizing
transmitter" vas built, t ested, and installed at the 11onticc110 plant on the
meteorological twer about nine months ago. %c " digitizing transmitter" operation
has been reasonably successful for the purpose intended, but it has not been It was
suitabic for use for submittals to the NRC, such as Appendix I compliance.
also intended that a teletypewriter vould he provided in the Monticello control
room to provide supplemental recording of the " digitizing transmitter" information.
It should be noted that the Monticello control room circady has a wind dircetion
and velocity recorder in operation. Since the teletypcuriter system is based
on use of the prototype device, which might be replaced with more suitabic equip-
ment, it has been decided not to install this supplemental equipment in the
Monticello control room. Met corological data continues to be obtained f rcnr. the
300' tower in strip chart form and is retained in accordance with recordkeeping
r equi r eane nt s .
Paragraph h on page 12 reference a ccmputer printout as being availabic, but not
in use. This is information fro the prototype "digitining transmitter" equipment
and is not in a format or of the juality which could be put to beneficial use by
the nuclear plant. It should also be noted that the licensec is currently hand
reducing data from the meteorological strip charts in order to obtain a full year
of acceptabic quality meteorological data in connection with the Appendix I
compliance submittal. This information will update the meteorological data that
'
, has been provided to the NRC in earlier submittals. .
l _P_ age 6, paranraph 3. a ,
i Since the Monticello plant does not have Appendix D Technical Specifications, the
- connent in regard to EGAD maintaining cognizance of aquatic biota protection con-
'
ditions, reporting to NSS when protection conditions are exceeded, etc., is not
applicabic to the Monticello plant at the present time,
e The NSS Department <loca not have administrative responsibility f or non-radiological
sampling as mentioned in the second sub-paragraph. The NSS responsibility for
reduc t ioti and cunputer processing of the untcorological program results is not a
.
routine renponnihility but resnited from the needs for obtaining this information
on a one-time basis for the Appendix 1 compliance submittal. The NSS Department
has not initiated development of calculational procedures for donc pathway report-
ing to the NRC in line with dircussion in an earlier paragraph that there are no
requirements for this at Monticello.
l
'
.
!
I
t
e
-_ _
.* NORTHERN OTATED POWER COM18ANY
_
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- .
. . . ,
,
'
.
.
,
fir James !! Atlan
Page 3 .
4
April 27.1970
Panc 7. onranraph c_* .
We are not aware of any computerized system used by the NSS Department for report-
ing the renults of program audits and inspections to supervision and manage;nent for
their review.
Panc 8, parnnraph 5
A revircd Radiation Environmental !!onitoring Program uns submitted to the Commission
<
on October 15, 1975 as a license amendment request; the program hoc not yet been
put into ef fect since the license amendment has not been issued by the !!nc. The
. March 1, 1976 submittal referenced in the inspection report involves interim
Technical Specifications on radioactive ef fluents; the nadiation F.nvironmental
Monitoring Technical Specification pages that were included with the !! arch 1,1976
cubmittal ucre included only because there are changes in pagination in this section
due to the removal of radioactive offluents from Appent _x A and their transfer to
Appendix B.
Pancs 9-11, paranraph d
'
The inspection report correctly reficcts the increases in Icvels of I-131 in milk
during the summer of 1975; however, it does not point out that these Icvels have
. been greatly reduced since replacement of the defective initial 7x7 fuel during
the refueling outage in October, 1975.
On the bottom of page 10 and the top of page 11, still under paragraph d, there is
a discussion of the number of iodine sampics which should be included in the
averaging to determine if additional reporting is required on estimates of likely
exposures to individuals and population groups. The Technical Specification re-
quirement for supplemental reporting is based on the likelihood of intahes in
excess of 17. of thosc that could result from continuous exposures to the concon-
tration values of Appendix B, Tabic II, Part 20. This appears to be similar to
design objective reporting. It is our position that the sampics should be
averaged over a calendar quarter and if the average concentrations of I-131 in
milk are greater than 2.4pci/1, then the supplementn1 information would be required.
Yours very truly,
b. & ff
'
L O Mayor, PE
Manager of Nuclear Support Scryices
.
1DM/ak
.
cc: Victor Stello
C Charnorf
MPCA - Attu: J W Ferman
.
e
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