ML20054B724
| ML20054B724 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/15/1982 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.4.2, TASK-2.F.1, TASK-2.K.3.15, TASK-2.K.3.22, TASK-2.K.3.24, TASK-2.K.3.27, TASK-TM GL-82-05, GL-82-5, NUDOCS 8204190128 | |
| Download: ML20054B724 (6) | |
Text
.
o i
/
PHILADELPHIA ELECTRIC COMPANY p,
D 23O1 M ARKET STREET g
P.O. BOX 8699 QggG;p,g PHILADELPHIA. PA.19101
~~
A pg 1 6 1932, -
a, SHIELDS L DALTROFF f7 aus*5c"//EEo rag 4
O
^
April 15, 1982 RE:
Docket Nos. 50-277 50-278 Mr. Darrell G.
Eisenhut Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Subject :
Response to Generic Letter No. 82-05 Post-TMI Requirements
Dear Mr. Eisenhat:
This letter transmits information requested in Generic Letter No. 82-05, D.
G.
Eisenhut to All Licensees of Operating Power Reactors, dated March 17, 1982, concerning implementation of selected NUREG-0737, TMI Action Plan Requirements.
Information regarding NUREG-0737 items for which modifications or engineering studies have been completed is presented in Table 1.
Information regarding pending NUREG-0737 items is provided in i
Table 2.
The proposed implementation dates represent our current estimate for completion of the work, and may be revised for reasons beyond our control; i.e.,
delays in equipment delivery or unforeseen mechanical problems.
As identified in Table 2, we have revised the expected completion date for the wide range containment water level monitor, Item II.F.1(5) to June 30, 1982 as a result of the recent manufacturer's notification that the 1
Oh i
h!(
8204190128 820415 PDR ADOCK 05000277 l
P PDR
e 9
f a
1 Mr. Darrell G.
Eisenhut Page 2 l
l i
shipment date for the level transmitters has been delayed until early May 1982.
The previous expected completion date was April 30, 1982 ( S.
L.
Daltroff to D.
G.
Eisenhut, dated February 19, 1982).
All modifications regarding NUREG-0737 items in Enclosure 1 of Generic Letter No. 82-05, for which we have made previous commitments, are expected to be completed within the next several months.
Should you have any questions regarding this matter, please do not hesitate to contact us.
l 1
1 Sincerel y,
,.]
l
, [,) W j
s 4
i i
l i
k i
i 1
f-W' o
d e
TA3LE I COMPLITED NUREG 0737 ITEMS - P:- AC:! BOTTOM STATION Iten/ Title Requirement Nureg-0757 Status (1)
Schedule I A 3.1 S i ra.:l a t o r Exams Incluce s i:n u l a t o r exams 10-1 S1 Simulator exam' will be used in licensing examinations starting with
- e first license examinations f-ilowing 10-1-81 currently scheduled for May 1982.
II.B.2 Plant Scheduling Modify Facility to provide 1-1-82 Study completed.
Concluded that access to vital areas current design provides access under accident conditions to vital areas under accident conditions (1-2-80, 1-31-80, 10-15-80, 1-5-31) therefore modifications are not deemed to be necessary.
I B. 4 Training for Complete training program 10-1-82 Initial training completed Mitigating Core 11-5-80.
An improved training Damage program completed 10-2-81.
11 E.4.2 Con t a inir en t Lower containment pressure 7-1-81 Study concluded that current IsolatJon serpoint to level setpoint compatible with normal Dependability -
coupatible with normal operation (1-8-81).
NRC Part 5 operation concurred in a 12-15-81~1etter from J.
F.
Stolz.
II.F.1(1) Accident Install noble gas effluent 1-1-82 Completed 1-51-80.
- Letter, Monitoring monitors dated 2-8-81.
from J.
F.
Stolz approved licensee's actions on this issue.
e o
TABLE 1 (Cont'd COMPLETED NUREG-0737 ITEMS - PEACl! BOTTOM STATION Nureg-0737 Item / Title Requirement Schedule Status (1)
II.F.I (6) Accident Provide continuous 1-1-82 Existing CAD hydrogen analyzer Monitoring indication of hydrogen meets the NRC design criteria concentration in contain-except for verification of ment environmental qualification.
Qualification will be established as part of the Bulletin 79-01B program (12-23-81)
II.K.3.1S Isclation of Modify pipe break 7-1-81 Completed llPCI/RCIC detection logic to prevent Unit 2:
4-30-81 inadvertent isolation.
Unit 3:
9-2-81 (refueling outage)
II.K.3.24 Space Cooling Confirm adequacy of space 1-1-82 Study concluded that current for liPCI/RCIC cooling for ilPCI/RCIC design meets the NRC criteria (6-26-81)
II.K.3.27 Common Provide common reference 7-1-81 Completed September 1980 Reference Level level for vessel level (10-2-80) instrumentation.
Note (1):
Dates in parenthesis refer to the date of the Philadelphia Electric Company's submittal to the NRC regarding that NUREG 0737 issue.
=~ -
?
a
_ _ _.. _ _. =., _... _. _.
4 i
I J
TABLE 2 PENDING NUREG-0737 ITEMS - PEACH BOTTOM STATION ItemiTitle Requirement Nureg-0737 PECo. Proposed Need for Schedule Justification and/or Schedule Schedule Adjustment (1)
Compensatory Heasures II.8.3 Install upgraded 1-1-82 Unit 2: current re-Time requirements Interim sampling and counting pro-Post-accident fueling associated with the cedures implemented on 1-14-80 that Post 1
C8Pability outage installation of eleven improve our capability for post-Accident I
Unit 3: 4,30-82 new sample lines.
accident sampling Sampling II.E.4.2 Isolate purge and 7-1-81 Not Applicable Not Applicable PECO's 12-22-80 submittal awaiting Containment vent valves on NRC review.
Submittal informed Isolation radiation signal NHC that the Peach Bottom valves Depenstabil-close on reactor building high I
ity radiation exhaust, and further Part 7 clarification was requested.
PECo i
working hith BWR Owners' Group to provide a technical bases for an 4
alternative to a drywell exhaust high radiation trip.
II.F.1 (2)
Provide capability 1-1-82 6/30/82 Need for further NRC Interim sampling 6 counting pro-Accident for effluent moni-clarification, and cedures implemented on 1-14-80 Monitoring toring of iodine, improvements in the that improved our capability of j
state-of-art capabili-analyzing iodine 6 particulate i
ty to retrieve a highly filters under accident conditions.
radioactive sample
]
delayed implementation.
(ll-3-SI) 4 f
i 4
1 l
l l
TABLE 2 (Cont'd)
PENDING NUREG-0737 ITEMS - PEACH BOTTOM STATION Item / Title Requirement Nureg-0737 PECo Proposed Need for Schedule Justification and/or Schedule Schedule Adjustment (1)
Compensatory Neasures II.F.1.(3)
Install in-contain-1-1-82 Unit 2: current re-Completion of work Other parameters are Accident Monitor-ment radiation-level fueling outage requires a plant outage.
available for detecting ing monitors Schedule revision pro-an accident situation.
Unit 3: completed posed to coordinate this Dec. 1981 activity with current re-fueling outage (9-4-81)
I I. F.1 (4 )
Provide continuous 1-1-82 Two channels of contain-Accident Monitor-indication of contain-Unit 2: current re-Same as for item II.F.1 ment pressure indication ing ment pressure fueling outage (3)
(0-70 psig) are currently Unit 3: completed operational.
11-17-81 II.F.1(S)
Provide continuous 1-1-82 Unit 2: current re-Time restraints associ-Two channels of narrom Accident Monitor-indication of contain-fueling outage ated with the development range level monitors ing ment water level Unit 3:
four weeks of environmentally (qualified) are currently after delivery of qualified equipment.
operational. Tho channel-level transmitters.
Delivery of level trans-of wide range level moni-Complet ion expected mitters delayed by vendor tors (non-qualified) are by 6-30-82 currently operational.
II.K.3.22 Modify design of RCIC 1-1-82 Unit 2: current re-lSame as for item II.F.1 (1) Manual capability to RCIC Suction suction to provide fueling outage l(3) t ransfer RCIC suction automatic transfer to Unit 3: completed I
exists (procedure approscJ torus.
9-23-81 I
11-13-801 l
(2) til'C l system a s a l l a til e I
w it h aut on:et ie suet ion l
t ran s fer capability.
Note (1) Dates in parenthesis refer to the date of Philadelphia Electric Company's submittal to the NRC regarding that NUREG 073~ issue.
x
-