ML20206E941
| ML20206E941 | |
| Person / Time | |
|---|---|
| Issue date: | 04/29/1999 |
| From: | Beckner W NRC (Affiliation Not Assigned) |
| To: | Jennifer Davis NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT & |
| References | |
| NUDOCS 9905050292 | |
| Download: ML20206E941 (5) | |
Text
.
a.
April 29, 1999 Mr. James Davis Nuclear Energy institute 1
1776 Eye Street, NW Suite 300 Washington, DC 20006-2496
Dear Mr. Davis:
This letter is to inform you of a change in disposition for TSTF-021, Revision 1. The recommendation to approve TSTF-021, R.1, is incorrect The disposition should be to Modify.
Approval of TSTF-021 and rejechon of TSTF-022 was followed by the submittal of TSTF-021, R.1. TSTF-022 requested that brackets be placed around the flow rate contained in the surveillance. TSTF-022 was rejected based on the staff posebon that those specifications that currently contain a flow rate should retain them. Subsequently, following rejection of TSTF-022, TSTF-021, R.1 was revised to delete the flow rate contained in the surveillance even though it had been rejected in TSTF-022. Therefore, the disposition of this revision (TSTF-021, R.1) should have been to Modify the TSTF to reject the deletion of the flow rate in the surveillance. This change is consistent with NRC disposition of TSTF-022. The licensees should retain their licensing basis. We understand the difficulty in meeting the flowrate when the RHR it., aligned to the RWST. To address this problem, we propose adding notes to those specifications contaming flow rates as indicated in the attached information.
Please revise your records to reflect the changed disposition and restoration of the flow rate to the standard technical specifications.
Sincerely, Original Sign:d By William D. Beckner, Chief Technical Specifications Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation
Enclosure:
As stated cc:
N. Clarkson, BWOG DISTRIBUTION:
(f f[
j
\\
e Center D. Wuokko, BWOG Fil B. Ford, BWROG PUBLIC T. Weber, CEOG TSB Reading File D. Buschbaumh, WOG WDBeckner D. Hoffman, EXCEL TSB Staff
)OCUMENT NAME: 0 \\DLJ\\TSTFCH21.WPD a
OFFICE RTSB/ DRIP /NRR.
RTSB/DRlP/NRR >
C:RTSB/ DRIP /NRR NAME MWWestonM RLDentiid (2 WDB'ckner wo6
'g~
DATE 4/22/99 04/ % /39 04/.07/99 9
OFFICIAL RECORD COPY t\\,) er 5D 0(
V nq0 pm-9905050292 990429 REVQPERGyMyC PDR
- ,.s\\
UNITED STATES p
NUCLEAR REGULATORY COMMISSION I
wAsMNGTON, D.C. 30se6mm April 29, 1999 Mr. James Davis Nuclear Energy Institute 1776 Eye Street, NW Suite 300 Washington, DC 20006-24g6 I
Dear Mr. Davis:
This letter is to inform you of a change in disposition for TSTF-021, Revision 1. The recommendat.a to approve TSTF-021, R.1, is incorrect. The disposition should be to Modify.
Approval of TSTF-021 and rejection of TSTF-022 was followed by the submittal of TSTF-021, R.1. TSTF-022 requested that brackets be placed around the flow rate contained in the surveillance. TSTF-022 was rejected based on the staff position that those specifications that currently contain a flow rate should retain them. Subsequently, following rejection of TSTF-022, TSTF-021, R.1 was revised to delete the flow rate contained in the surveillance even though it had been rejected in TSTF-022. Therefore, the disposition of this revision (TSTF-021, R.1) should have been to Modify the TSTF to reject the deletion of the flow rate in the surveillance. This change is consistent with NRC disposition of TSTF-022. The licensees should retain their licensing basis. We understand the difficulty in meeting the flowrate when the RHR is aligned to the RWST. To address this problem, we propose adding notes to those specifications containing flow rates as indicated in the attached information.
Please revise your records to reflect the changed disposition and restoration of the flow rate to the standard technical specifications.
Sincerely, yh : O. hW William D. Beckner, Chief Technical Specifications Branch i
Division of Regulatory improvement Programs j
Office of Nuclear Reactor Regulation
Enclosure:
As stated cc-N. Clarkson, BWOG D. Wuokko, BWOG ill. Ford, BWROG T. Weber, CEOG D. Buschbaum, WOG D. Hoffman, EXCEL
l j
insert TSTF-021, R.1 l
Insert under LCO NOTE The loop required to be in operation may be removed from operation and be considered OPERABLE:
a To support filling and draining the reactor cavity when aligned to, or during transitioning to or from, the refueling water storage tank provided the required RHR loop is capable of being realigned to the Reactor Coolant System (RCS): or b.
To support required testing provided the required RHR loop is capable of being realigned to the RCS I
l l
1 i
l l
l l
=
RHR and Coolant Circulation-Low Water Level i
3.9.6 g
3.9 REFUELING OPERATIONS
)
3.9.6 ' Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level LC0 3.9.5 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.
rnscwr Z.
APPLICABILITY:
MODE 6 with the water level < 23 ft above the top of reactor
[N5per(
vessel nange.
CTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Less than the required A.1 Initiate action to Immediately number of RHR loops restore required RHR OPERABLE.
loops to OPERABLE status.
g A.2 Initiate action to Immediately establish 1 23 ft of water above the top of reactor vessel flange,.
B.
No RHR loop in 8.1 Suspend operations Immediately operation.
involving a reduction in reactor coolant boron concentration.
AE1 (continued)
~
~
- ~.*~~ ~. *T :_ L.*
~"~ ~: 2.
- L
RHR and Coolant Circulation-Low Water Level 9
3.9.6 of ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
(continued) 8.2 Initiate action to Immediately restore one RHR loop to operation.
hm B.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.
SURVEILLANCE REQUIREMENTS 1
L.
SURVE!LLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> circulating reactor coolant at a flow rate of k (2800] gps.
SR 3.9.6.2 Verify correct breaker alignment and 7 days indicated power available to the required RHR pump that is not in operation.
i l
WOG STS 3.9-11 Rev I, 04/07/95
........--- =._
=
-