ML19210A395
| ML19210A395 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/07/1977 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19210A396 | List: |
| References | |
| GQL-0020, GQL-20, NUDOCS 7910290621 | |
| Download: ML19210A395 (4) | |
Text
,
NRd ropu 195 U.S. NUCLE AR REGUL ATORY COS
'SSIO N DOCKET NUM BE R a-7s>
50-289 NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL TO:
R. W. Reid FROM: Met. Ed. Co.
DAT,E OF DCCUMENT e7-77 Reading, Pa.
19603 R.C. Arnold DATE C
ED g_
M ETTER ONOTORIZED PROP INPUT FORM s* UMBER OF COPIES RECE4VED
@RIGIN AL DNCLASSIFIED CcOPY 3 OISOOd'37 bb DESCRIPTION Ltr trans Cl',e following:
EN CLOSU RE Tech Spec Change Request No. 43, Amde
- 1 notarized 1-7-77 consist of replacement (3P) pages for Appendix A containing changes to incorporate steam generators operating &
inservice inspection requirements into THI-1 TechSpecs......(3 Orig & 37 CC)
(14P)
CERTIFICATE OF SERVICE dated 1-7-77 shuoing av of Tech Spec Change upon Mr. W. B. Archart, Bd,
of Supvr of Londonderry Township, Middletown, Pa. e.t al.....(1 Orig & 39 CC)
(IP)
' 3 W U.r.:t3r 4 pt' PLANT HAME:
Three Mile Island Unit 1 M
lh SAFETY FOR ACTION /INFORMATION ruvTon DHL I-19-77 ASSIGNED AD:
,s A99TFWn_AD*
lE6NCH CHIEFr
[8 K f. t d -
RRANrit ciTTT'?-
R QJECT MANAGER:
1 h3 @.if. i 4 PROJECT MANAGER:
LIC. ASST. :
TAl4 y Ad LIC. ASST. :
w I
INTERNAL DISTRIBUTION k PlG FIT D SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY &
I I NRC PDR HEINEMAN TEDESCO ENVIRO ANALYSIS X I&E [:3, SCHROEDER BENAROYA DENTON & WT T TR i
OELD TATNAS GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH.
I IIIPC MACARRY KIRKWOOD ERNST i
CASE KNIG11T BALLARD I
HANAUER SIINEIL OPERATING REACTORS SPANGLER
!!AP.LESS PAWLICKI STELLO SITE TECH.
PROJECT MANAGEMENT REACTOR SAFETY OPERATING TECH.
GAMMILL i
BOYD ROSS X EISENHUT STEPP P. COLLINS NOVAK SHAO HULMAN I
I H0_USTON ROSZTOCZY
_HAER PETERSON CHECK BUTLER SITE ANALYSIS I
MELTZ X
GRIMES VOLLMER i
HELTEMES AT & I BUNCH
_]
SKOVHOLT SALTZMAN
% J. COLLINS i
RUTBERG I
KREGER I
~
EXTERNAL DISTRIBUTION CONTROL NUMBER i
}PDR: Marrbhurg. Pa.
NAT. LAB:
BROQ_KJJAYEILNAT. TAR.
TIC:
REG V.IE ULRIKSON (ORNL) 316 NSIC:
LA PDR
- 3ELT d4f f3
-7 910 T9 Oh, ; ].
ASLB:.,
CONSULTANTS :
KACRS /InCYS g
/
i
E
$YS
~
Regulakrf Dcd i r,38 METROPOLil AN EDISON COMPANY POST OFFICE BOX 5,4
~NNSYLVANI A 19603 TELEPHONE 215 - 929-3601
.; ~ ' '
S January ~, 1977 tM CQL 0020
.4 4
r s
M c
Q
,@s:
- C ',$l],' ".
f )n_
\\,'w n,,.,s 4
i \\
k Am\\..:.1.-:', '
N
.s
,.. 5 N
fr -,'%
9 ca.' ' '
6', '
F," g i. @. %sN.>.
S-dN
. E
),
' V-4 N_'
r;f C
JAN1 ' W.
a d Reactor Regulati k b
gyi,q(.8p,#
~
Direc.'N Attn:
R.
a.
neid, Chief 1, Ws, yg, gwon 3 y
ce 7
Operating Reactors Branch !o. h M'
- w%
. 7l g.
U. S. !!uclear Regulatory Commission
'A N7 f'
t'd' c ['
Washington, D. C.
20555
......1'
'~ 'g
Dear dir:
Three Mle Island !!uelear Station, Unit 1 (TMI-1)
Docket !c. 50-289 Operating License !!o. DPR-50 Technical Specification Change Request :To. h3, Amendment 1 Enclosed are three signed originals (sixty conformed copies sent separately) of Technical Specification Change Request !!o. h3, Amendment 1, requesting anendment to Appendix A of Operating License Iio. DPR-50.
As a part of this request, proposed replacement pages for Appendix A are enclosed.
Also enclosed is one signed copy of Certificate of Service for proposed Technical Specification Change Request ?!o. h3, Amendment 1, to the chief executives of the township and county in which the facility is located.
As requested by your letter of December lh, 1976, following please find a listing of our justifications for differences between this proposed change request and the model technical specifications submitted with your letter of September 1k, 1976, a.
Reference Model T.S. 3.h.5.2 & h.h.5.6 A steam generator water level limitation requirement is not pro-posed. Steam generator water level serves no function in monitoring tube degradation. The model technical specification for this requirement, "The steam generator water level limits are consistent with the initial assumptions in the FSAR", does not apply to 2!I-1 since no such assumptions were made in the ZII-l FSAR.
1469 106 316
TS h3, Am. 1 2
1/7/77 GQL 0020 b.
Reference Model T.S. No. 3.h.5.1 & 2 - Action a.
The T above which the reactor coolant system (RCS) cannot be gyg heated unless e.11 inoperable steam generators have been restored to the OPERABLE status (TMI-1 TS 3.1.1.2), was changed to 250 F.
This change is needed since TS 3.1.1.2 correlates with TS 3.h.
The main basis for TS 3.h rests on the fact that at TMI-l normal decay heat removal is by the steam generator with the steam dump to the condenser when system temperature is above 2500 F and by the decay heat removal system when system temperature is below 2500 F.
c.
Reference Model T.S. No. h.h.5.2 A 1 % sample sise is proposed. The proposed sample sise, inspection results categories, etc., are based on ASME Code Section XI, Winter 1975 Addenda.
A 1 % sample sise is suggested by the ASVE Code on Table IWB-2500, Category B-Q.
We feel that the ASME Coue Section XI is an induitry accepted standard which has been accepted by the USNRC on many occasions. We do not see any reason why the submit-ed model technical specification should differ extensively with the ASME Code and, in scme cases, even with USNEC Regulatory Guide 1.83 (inspection results categories). We are, therefore, requesting a reasonable justification to support these differences if total compliance to the submitted model technical specifications should be required.
d.
Reference Model T.S. No. k.h.5.2.a This requirement is being deleted. Possible generic problems related to the steam generators should be handled on a case basis in cooperation with the NEC but should not be part of Technical Speci-fications. The NRC Office of Inspection and Enforcement IE Bulletins /
Circulars Program has successfully handled these problems in the past and we do not see any *asons why it should be handled differently in this case.
e.
Reference Model T.S. No. h.h.5.2.b & c The proposed requirements are consistent with ASME Section XI, Winter 1975 Addenda, IWB-2h30 and Table IWB-2500-Category BQ.
As referenced in "c" above, we feel that a justification to support the model technical specification and its differences from ASME Code Section XI and USNRC Regulatory Guide 1.63 is necessary if total compliance should be required.
}kh9
T3 4.', Am. 1 3
1/7/77 GOL 0020 f.
Reference Model T.C "o. h.h.5.3.b The proposed criteria for acceptability of a '..ty-month inspection interval are consistent with the ACME Code Section XI I'4B-2h20 (d).
As referenced in "c" and "e" abova, a reaconable Jr.stification should be provided if total compliance is required.
g.
Reference Model T.S. Table k.h-2 The proposed Table h.18.2 differa from the model technical specifi-cation due to the use of ASME Code Cection XI as the bacio for our inspectiot. results categories.
Sincerely, R. C. Arnold Vice President RCA:JMC:eg
Enclosures:
(1) Technical Specification Change Request 3o. h3, Am. 1 (2) Certificate of Service of Technical Specification Change Request No. h3, A=endment 1 ghh t