ML19210A601: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 21: | Line 21: | ||
U.S. NUCLEAR REGULATORY CCM N , COCKET NUMBE R I NRC PoRu 195 | U.S. NUCLEAR REGULATORY CCM N , COCKET NUMBE R I NRC PoRu 195 | ||
:':asi 54 - .283 ! | :':asi 54 - .283 ! | ||
' NRC' DISTRIBUTION FOR PART 50 DOCKET MATERIAL FROM: cATE CP CCCUMENT I TO: | |||
' NRC' | |||
DISTRIBUTION FOR PART 50 DOCKET MATERIAL FROM: cATE CP CCCUMENT I TO: | |||
Metropolitan Edison Company 10/21/77 ! | Metropolitan Edison Company 10/21/77 ! | ||
Mr. R. W. Reid Reading, Pa. DATE RECEIVE D | Mr. R. W. Reid Reading, Pa. DATE RECEIVE D | ||
Line 32: | Line 28: | ||
@;,ETTER C NCTO R IZ E D PRCP tNPUT PoRM NUM8ER oF CCPIES RECEIVED l | @;,ETTER C NCTO R IZ E D PRCP tNPUT PoRM NUM8ER oF CCPIES RECEIVED l | ||
/CRIQiNAL [}UNC LASSIFI E D CCCPv l$sp@ | /CRIQiNAL [}UNC LASSIFI E D CCCPv l$sp@ | ||
ESC RIPTIC N EN CLOSU R E | ESC RIPTIC N EN CLOSU R E e | ||
Consists of the Porter-Gertz Report (PGC- | |||
! TR-108) furnished for NRC info. in Connection with requested evaluation of the Tech Specs | |||
! TR-108) furnished for NRC info. in Connection | |||
with requested evaluation of the Tech Specs | |||
* l | * l | ||
' Change Recuest on off-site doses Calculated in the TMI-l Appendix I Analysis... | ' Change Recuest on off-site doses Calculated in the TMI-l Appendix I Analysis... | ||
l t | l t | ||
(1-P) (13-P) . | (1-P) (13-P) . | ||
APPENDIX I DISTRIBUTION AFTER ISSUANCE OF A 1492 104 | APPENDIX I DISTRIBUTION AFTER ISSUANCE OF A 1492 104 | ||
: LICENSE Three Mile Island Unit No.1 PLANT NAME:,* RJL 10/26/77 c I EA3CLA /h*40-m -ho SAFETY FOR ACTION /INFORMATION . I 1 BRANCH CHIEF: (2) (S")l /PE/o I I FR M ; l | |||
: LICENSE Three Mile Island Unit No.1 PLANT NAME:,* RJL 10/26/77 c I EA3CLA /h*40-m -ho SAFETY FOR ACTION /INFORMATION . I | |||
1 BRANCH CHIEF: (2) (S")l /PE/o I I FR M ; l | |||
.w a. n: | .w a. n: | ||
I I L::. 4:2?- | I I L::. 4:2?- | ||
Line 62: | Line 50: | ||
~ | ~ | ||
1 1 i ! ! l t i i l i I i i i i i e i i i l I i : | 1 1 i ! ! l t i i l i I i i i i i e i i i l I i : | ||
! I i l i I i EXTERNAL DISTRIBUTICN I CONTROL NUMBER , | ! I i l i I i EXTERNAL DISTRIBUTICN I CONTROL NUMBER , | ||
.I LPDR: }/MP/fADA?r. f/7 . I i < | .I LPDR: }/MP/fADA?r. f/7 . I i < | ||
l T!C 1 I i i m | |||
l T!C 1 I i | |||
i m | |||
' l A 0r< S /[o CY9 erN* ch- +.rnv .# | ' l A 0r< S /[o CY9 erN* ch- +.rnv .# | ||
l 1 ? "'1080bf34 | l 1 ? "'1080bf34 | ||
/ p i l l .[ ! I r | / p i l l .[ ! I r | ||
YN ff;] ~ | YN ff;] ~ | ||
? | ? | ||
49 ~.-.. I0d9 DOCKETFilEC METROPOLI FAN EDISON COMPANY POST OFFICE BOX SO READING. PENNSYLVANIA 19603 TELEPHONE 215 - 929 0601 October 21, 1977 $ | |||
49 ~.-.. I0d9 DOCKETFilEC METROPOLI FAN EDISON COMPANY | |||
POST OFFICE BOX SO READING. PENNSYLVANIA 19603 TELEPHONE 215 - 929 0601 October 21, 1977 $ | |||
GQL 1389 * | GQL 1389 * | ||
< b ' nD* ' | < b ' nD* ' | ||
Line 96: | Line 70: | ||
'! -2 Orerating Reseters Branch No. k | '! -2 Orerating Reseters Branch No. k | ||
/ A | / A | ||
.; N4 Ogh o ' | .; N4 Ogh o ' | ||
U. S. Nuclear Regulatory Cc==ission [- Jy Washington, D.C. 20555 x f . w,._ A | U. S. Nuclear Regulatory Cc==ission [- Jy Washington, D.C. 20555 x f . w,._ A | ||
Line 103: | Line 76: | ||
==Dear Sir:== | ==Dear Sir:== | ||
N , | N , | ||
Three Mile Island Nuclear Station Unit 1 Cperating License No. DPR-50 Docket No. 50-269 Ycur letter of August 19, 1977 requested that Met-Ed evalaa'e the effect of the Technical Specification Change Request on off-site doses calculated in the TMI-1 Appendix I Analysis. It is our conclusion that there vill be no change in Appendix I dose predictions. Appendix I does not assune re-leases at Technical Specificaticn limits, but rather calculates the expected releases based on station characteristics and average operating ecnditions. | Three Mile Island Nuclear Station Unit 1 Cperating License No. DPR-50 Docket No. 50-269 Ycur letter of August 19, 1977 requested that Met-Ed evalaa'e the effect of the Technical Specification Change Request on off-site doses calculated in the TMI-1 Appendix I Analysis. It is our conclusion that there vill be no change in Appendix I dose predictions. Appendix I does not assune re-leases at Technical Specificaticn limits, but rather calculates the expected releases based on station characteristics and average operating ecnditions. | ||
Since there vill be no modification to, or change in the operatien of, the TMI-l Radicactive Waste Treatment System as a result of this change request, this Technical Specification Change Request vill not affect the off-site dose within the centext of Appendix I. | Since there vill be no modification to, or change in the operatien of, the TMI-l Radicactive Waste Treatment System as a result of this change request, this Technical Specification Change Request vill not affect the off-site dose within the centext of Appendix I. | ||
Line 115: | Line 83: | ||
/ ,/ | / ,/ | ||
/J. 3. Herbein | /J. 3. Herbein | ||
/ Vice President JGE:DGM:tas Attachment | / Vice President JGE:DGM:tas Attachment | ||
} ; : ._}} | } ; : ._}} |
Latest revision as of 05:52, 2 February 2020
ML19210A601 | |
Person / Time | |
---|---|
Site: | Three Mile Island ![]() |
Issue date: | 10/21/1977 |
From: | Herbein J METROPOLITAN EDISON CO. |
To: | Reid R Office of Nuclear Reactor Regulation |
Shared Package | |
ML19210A602 | List: |
References | |
NUDOCS 7910300639 | |
Download: ML19210A601 (2) | |
Text
.
~
U.S. NUCLEAR REGULATORY CCM N , COCKET NUMBE R I NRC PoRu 195
- ':asi 54 - .283 !
' NRC' DISTRIBUTION FOR PART 50 DOCKET MATERIAL FROM: cATE CP CCCUMENT I TO:
Metropolitan Edison Company 10/21/77 !
Mr. R. W. Reid Reading, Pa. DATE RECEIVE D
. J. G. Herbein -
10/26/77
@;,ETTER C NCTO R IZ E D PRCP tNPUT PoRM NUM8ER oF CCPIES RECEIVED l
/CRIQiNAL [}UNC LASSIFI E D CCCPv l$sp@
ESC RIPTIC N EN CLOSU R E e
Consists of the Porter-Gertz Report (PGC-
! TR-108) furnished for NRC info. in Connection with requested evaluation of the Tech Specs
- l
' Change Recuest on off-site doses Calculated in the TMI-l Appendix I Analysis...
l t
(1-P) (13-P) .
APPENDIX I DISTRIBUTION AFTER ISSUANCE OF A 1492 104
- LICENSE Three Mile Island Unit No.1 PLANT NAME:,* RJL 10/26/77 c I EA3CLA /h*40-m -ho SAFETY FOR ACTION /INFORMATION . I 1 BRANCH CHIEF: (2) (S")l /PE/o I I FR M ; l
.w a. n:
I I L::. 4:2?-
I
! I I 1
l l l l 1 I I I a
A INTERNAL DISTRIBUTION i CoFG FIL1 l il i I Tr<C 77 I l l i I
iICE (2) l I I I t l i i I OELD 1 1 _
I i l GOSSICK & STAFF l l l l l l i t BUTLER I I I GRUES l l l l 6 I DENTON (LTRI I l 1 l !
I BALLARD i l i i I G,MMILL 1 l 1 i
' I HULMAN l l l i i MARKEE l l l l i l
I i J. COLLINS (2) I i l l i l t I tarcen i l l I i nyr .: 1 I I i { l
~
1 1 i ! ! l t i i l i I i i i i i e i i i l I i :
! I i l i I i EXTERNAL DISTRIBUTICN I CONTROL NUMBER ,
.I LPDR: }/MP/fADA?r. f/7 . I i <
l T!C 1 I i i m
' l A 0r< S /[o CY9 erN* ch- +.rnv .#
l 1 ? "'1080bf34
/ p i l l .[ ! I r
YN ff;] ~
?
49 ~.-.. I0d9 DOCKETFilEC METROPOLI FAN EDISON COMPANY POST OFFICE BOX SO READING. PENNSYLVANIA 19603 TELEPHONE 215 - 929 0601 October 21, 1977 $
GQL 1389 *
< b ' nD* '
'\
/
~4r. R. W. Reid, Chief o
t.
/ !*
gC7 /Q n/~//Q./%
'! -2 Orerating Reseters Branch No. k
/ A
.; N4 Ogh o '
U. S. Nuclear Regulatory Cc==ission [- Jy Washington, D.C. 20555 x f . w,._ A
(
Dear Sir:
N ,
Three Mile Island Nuclear Station Unit 1 Cperating License No. DPR-50 Docket No. 50-269 Ycur letter of August 19, 1977 requested that Met-Ed evalaa'e the effect of the Technical Specification Change Request on off-site doses calculated in the TMI-1 Appendix I Analysis. It is our conclusion that there vill be no change in Appendix I dose predictions. Appendix I does not assune re-leases at Technical Specificaticn limits, but rather calculates the expected releases based on station characteristics and average operating ecnditions.
Since there vill be no modification to, or change in the operatien of, the TMI-l Radicactive Waste Treatment System as a result of this change request, this Technical Specification Change Request vill not affect the off-site dose within the centext of Appendix I.
The attached Porter-G-t: Report (PCC-TR-108) determines that drinking water is the critical dose pathway and that the limits we are requesting are less than the conservatively calculated MPCv's in the report. In addition the report calculates the dcse to an adult via four separate pathways in a sample problem on page B h. The concentrations used are ten times greater for Xe-133 and two times greater for Xe-135 than cur proposed release limits. The sample problem assumes a continual release at these less conservative limits for a year. The results shcw that the maximum possible dose to an adult from all pathways combined, would be less than 0 3 = rem /yr. In view of these calculations, we feel that the limits we are requesting are conservative, and that an occasional release at the proposed levels vill have a negligible effect en persons in the unrestricted area.
Sincerely,
/ ,/
/J. 3. Herbein
/ Vice President JGE:DGM:tas Attachment
} ; : ._