ML20210R702
| ML20210R702 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/12/1999 |
| From: | Lanksbury R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20210R706 | List: |
| References | |
| 50-282-99-06, 50-306-99-06, NUDOCS 9908170194 | |
| Download: ML20210R702 (3) | |
See also: IR 05000282/1999006
Text
g
>R Hai
UNITED STATES
/
g'e
[
'
NUCLEAR REGULATORY COMMISSION
n
REGION lil
5
]
801 WARRENVILLE ROAD
LISLE, ILLINOIS 60532-4351
\\*****/
August 12, 1999
Mr. M. Wadley
President, Nuclear Generation
Northern States Power Company
414 Nicollet Mall
Minneapolis, MN 55401
SUBJECT:
PRAIRIE ISLAND INSPECTION REPORT 50-282/99006(DRP);
50-306/99006(DRP)
Dear Mr. Wadley:
On July 20,1999, the NRC completed an inspection at your Prairie Island Nuclear Generating
Plant. The results of this inspection were discussed with Mr. D. Schuelke and other members
of your staff. The enclosed report presents the results of that inspection.
The inspection was an examination by the resident inspectors of activities conducted under
your license as they relate to reactor stafety, verification of performance indicators, event
followup, and to compliance with the Commission's rules and regulations and with the
conditions of your license. Within these areas, the inspection consisted of a selective
examination of procedures and representative records, observations of activities, and interviews
with personnel.
Based on the results of this inspection, one issue related to the potential effect of a high-energy
line break on control room habitability caused by a broken door was initially evaluated under the
risk significance determination and was found to have potential safety significance. This issue
i
has been entered into your corrective action program. Our final risk estimation will be
documented in a future inspection report. In addition, one issue related to improperly secured
Unit 1 containment sump hatches was categorized as being of low risk significance, although
regulatory requirements were violated. Therefore, one non-cited violation (NCV), consistent
with Appendix C of the Enforcement Policy, was identified. This issue has been entered into
your corrective action program. These two issues are list 96 in the unclosed summary of
findings and are discussed in the report.
]
The NCV discussed above is described in the subject inspection report. If you contest the
j
violation or severity level of the NCV, you should provkle a response within 30 days of the date
of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission,
i
l
ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional
Administrator, Region lil, the Director, Office of Enforcement, United States Nuclear Regulatory
Commission, Washington, DC 20555-0001, and the NRC Resident inspectors at the Prairie
Island facility.
i
9908170194 990812
ADOCK 05000282
G
.
.
. , -
.
~
1
M. Wadley
-2-'
i
in addition to the above, the inspection included a review and evaluation of the first quarte' of
- 1999 Performance Indicators. ' All Performance indicators were green wit l: tne exception of the
. Unit 2 Performance Indicator for Safety System Functional Failures v!nich was reported to be
- white with six falbres in the most recent four quarters. The indicator would have been white
from the first quarter of 1998 based on the historic data submitted with the first pilot plant
l
Performance Indicator submittal Of the six failures counted in the first quarter of the 1999
I
Performance Indicators submittal, five involved 10 CFR Part 50, Appendix R, fire protection
issues discovered in the second and third quarters of 1998. Those issues were all extensively
evaluated by the NRC in its fire protection functional inspection as discussed in Inspection
Report 50-282/98016(DRS); 50-306/98016(DRS). The NRC resolved the enforcement aspects
of the issues as discussed in a letter to you from the Regional Administrator, NRC Region lil,
dated March 30,1999 (EA 98-526). The NRC assessed the issues during the Plant
Performance Review as reported in a letter to you from the Director of Reactor Projects, NRC
Region lil, dated March 26,1999. The NRC plans no additional actions or inspections beyond
the. baseline inspection program because of those issues.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its
enclosure, and your response, if you choose to provide one, will be placed in the NRC Public
Document Room.
Sincerely,
/s/ R. D. Lanksbury
Roger Lanksbury, Chief
Reactor Projects Branch 5
Docket Nos. 50-282; 50-306
Enclosure:
Inspection Report 50-282/99006(DRP);
50-306/90006(DRP)
cc w/ encl:
Site General Manager, Prairie Island
Plant Manager, Prairie Island
i
- S. Minn, Commissioner, Minnesota
Department of Public Service
State Liaison Officer, State of Wisconsin
Tribal Council, Prairie Island Dakota Community
i
!
l
DOCUMENT NAME: G:\\PRAl\\PRA99006.DRP
To receive a co pr of this document , Indicato in the box *C' = Copy w/o attach /end *E' = Copy w/ attach / enc! *N' = No copy
OFFICE
Rlli
w
d6 Rill
QM l A)
l
NAME
KunowsliMt 7kje .
Lanksbury ~
DATE
8h2/99
8 4 /99
OFFICIAL RECORD COPY
..
.
.
.
.
!
!
M. Wadley
-3-
Q]stribution:
CAC (E-Mail)'
RPC (E-Mail)
Project Mgr., NRR w/enci
J. Caldwell, Rill w/ encl
B. Clayton, Rill w/enci
SRI Prairie Island w/ enc!
DRP w/enci
DRS w/enci
Rill PRR w/enci -
l
PUBLIC IE-01 w/enci
!
Docket File w/enci
GREENS
LEO (E-Mail)
DOCDESK (E-Mail)
1
I
l
l
1
6
1
3
17nnm;
.) \\
L
1
l
!
L..