ML20029E783
| ML20029E783 | |
| Person / Time | |
|---|---|
| Site: | 05200002 |
| Issue date: | 05/17/1994 |
| From: | Chu A Office of Nuclear Reactor Regulation |
| To: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9405200114 | |
| Download: ML20029E783 (5) | |
Text
-
(**
p-d O S
UNITED STATES 5
NUCLEAR REGULATORY COMMISSION k.....,/
WASHINGTON, D.C. 20555-0001 May 17.1994 MEMORANDUM FOR:
Christopher I. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support, NRR THRU:
F. Mark Reinhart, Section Chief Special Projects Section Technical Specifications Branch Division of Operating Reactor Support, NRR FROM:
Angela T. Chu, Reactor Engineer Technical Specifications Branch
)
Division of Operating Reactor Support, NRR
SUBJECT:
SUMMERY OF MEETING WITH ABB-CE ON CE SYSTEM 80+ TECHNICAL SPECIFICATIONS: APRIL 4-8, 1994 On April 4-8, 1994, the Technical Specifications Branch and its contractor, Brookhaven National Laboratory (BNL) met with ABB-CE to discuss some of the CE System 80+ technical specifications (TS) that were not resolved during the March 16-17, 1994 meeting between the staff and ABB-CE.
The discussions on CE System 80+ TS covered the following areas:
Alternate Protection System Diesel Generator (DG) Loss of Voltage Start (LOVS)
Crediting the combustion turbine generator (CTG) for DG outage TS format to be consistent with the Standard Technical Specifications (STS)
Reactor vessel level instrumentation in modes 4 and 5 Emergency diesel generator surveillance Final TS amendment submittal schedule Review of TS changes The probabilistic sensitivity study of an inoperable APS indicated a core damage frequency (CDF) increase of 18%. ABB-CE, therefore, agreed to maintain that TS and modified the surveillance requirements of performing a channel functional test on the Reactor Protection System to 31 days, a change from the proposed 92 days.
LOVS TS was modified from "per DG shall be OPERABLE" T0 "for each 4.16kv safety bus shall be OPERABLE".
CE System 80+ has four 4.16kv safety buses, not two as in most conventional plants.
This modification improves operational reliability while preserving the level of safety specified in the STS.
The probabilistic sensitivity study for crediting the CTG under the conditions of with or without tornado indicated a CDF increase of 1-4% which is considered as within the acceptable range of risk.
CE System 80+ has the MJC FBI ELBA fi4M
,p-99 f00
+v6Gua 9405200114 940517 PDR ADOCK 05200002
.\\
l A
Christopher 1. Grimes May 17, 1994 capability to reject 100 percent load, and the main turbine-generator will keep supplying house loads without challenging the DG, Furthermore, the contribution to CDF from Station Blackout and Loss of Offsite Power is significantly less than that of the ABWR.
Therefore, we agreed to extend the one DG outage time to be 14 days which is the same as the precedent ABWR.
ABB-CE also committed to provide surveillance requirements on the CTG similar to those of the ABWR.
The staff provided ABB-CE with assistance in following the Writer's Guide to modify the TS format so as to be consistent with the STS Format.
Inadequate instrumentation on the reactor coolant system level anc t;.e reactor vessel level can be a factor in the loss of shutdown cooling.
After discussions, CE rewrote this section of the TS to require operable instrumentation during modes 4 and 5 except while transitioning into mode 6.
A surveillance requirement was also added to perform Channel Check of the reactor vessel level every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Emergency diesel generator refueling interval surveillance requirements (SRs) in TS 3.8.1 and 3.8.2 were discussed.
The STS use a frequency of 18 months with a 1.25% extension.
During the discussion, CE proposed changes because l
this SR frequency with the extension did not allow sufficient flexibility for I
an 18 months fuel cycle with 3 months refueling outages.
As a result, the staff agreed to modify the SR frequency to 24 months without extension.
We discussed the schedule for the TS audit which is being performed by the Idaho National Engineering Laboratory (INEL).
ABB-CE will provide the final printed TS to the staff by mid-April; INEL will initiate the TS audit in mid-April; and the audit is expected to be complete in mid-May.
l The review of the final TS changes will be distributed to the technical staff, and 0TSB will coordinate a quick turn around review time. is a list of attendees for meetings from April 4-8, 1994.
3 Q
'btL i
Angela
. Chu, Reactor Engineer Special Projects Section Technical Specifications Branch Division of Operating Reactor Support, NRR
Enclosure:
As stated l
l
1 Enclosure Meeting Attendees April 4-8, 1994 ABB-CE Technical Specifications Meeting with NRC l
HAME ORGANIZATION Bob Rescorl ABB-CE I&C John Rec ABB-CE l
l Joe Congdon ABB-CE Tony Williams Duke Eng & SVCS Audrey Keshen ABB-CE Rupert Weston ABB-CE I
Millard Wohl NRC Mark Reinhart NRC Angela Chu NRC Mary Lynn Reardon NRC Pranab Samanta BNL Inn Kim BNL l
l l
I 4.__.
t, Christopher I. Grimes DISTRIBUTION w/ enclosures:
Central Files MSchwartz CERossi BABoger OTSB Staff WTRussell SAVarga JAZwolinski FJCongel CMarco LAReyes JWRoe EGAdensam DMCrutchfield PDR ACThadani JACalvo MJVirgilio DPAllison, CRGR OTSB R/F CIGrimes GClainas MWHodges JHConran, CRGR DORS R/F l.
1
/
I Christopher 1. Grimes May 17,1994 capability to reject 100 percent load, and the main turbine-generator will l
keep supplying house loads without challenging the DG.
Furthermore, the l
contribution to CDF from Station Blackout and Loss of Offsite Power is I
significantly less than that of the ABWR.
Therefore, we agreed to extend the one DG outage time to be 14 days which is the same as the precedent ABWR, ABB-CE also committed to provide surveillance requirements on the CTG similar to those of the ABWR.
The staff provided ABB-CE with assistance in following the Writer's Guide to modify the TS format so as to be consistent with the STS Format.
Inadequate instrumentation on the reactor coolant system level and the reactor vessel level can be a factor in the loss of shutdown cooling. After l
discussions, CE rewrote this section of the TS to require operable l
instrumentation during modes 4 and 5 except while transitioning into mode 6.
l A surveillance requirement was also added to perform Channel Check of the reactor vessel level every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
j Emergency diesel generator refueling interval surveillance requirements (SRs) in TS 3.8.1 and 3.8.2 were discussed.
The STS use a frequency of 18 months with a 1.25% extension.
During the discussion, CE proposed changes because l
this SR frequency with the extension did not allow sufficient flexibility for an 18 months fuel cycle with 3 months refueling outages.
As a result, the staff agreed to modify the SR frequency to 24 months without extension.
We discussed the schedule for the TS audit which is being performed by the l
l Idaho National Engineering Laboratory (INEL).
ABB-CE will provide the final l
printed TS to the staff by mid-April; INEL will initiate the TS audit in mid-l April; and the audit is expected to be complete in mid-May.
The review of the final TS changes will be distributed to the technical staff, and 0TSB will coordinate a quick turn around review time. is a list of attendees for meetings from April 4-8, 1994.
Original signed by:
l Angela T. Chu, Reactor Engineer Special Projects Section Technical Specifications Branch Division of Operating Reactor Support, NRR
Enclosure:
As stated l
DISTRIBUTION w/ enclosures:
Please see attached DOCUMENT NAME:
G:\\CE-CTG 2
- see previous concurrence OTSB: DORS:NRR SC:0TSB:00RS NRS FMReinhart[//[
l ATChu*
05/13/94 05/H/94 l
- -