ML20062A551
| ML20062A551 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/10/1990 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | Carns N ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20062A554 | List: |
| References | |
| NUDOCS 9010220164 | |
| Download: ML20062A551 (6) | |
Text
[".
Neil S. Carns 2.-
October 10, 1990 d.
EDG reliability program meeting, as a minimum, the guidelines of R.G. 1.155, c.
Equipment and components required to cope with an SB0 are incorporated in a QA program that meets the guidance of R.G. 1.155, Appendix A, and f.
Actions taken pertaining to the specific recomunendations noted in the SER.
The guidance provided on Technical Specifications (TS) for an SB0 states that the TS should be consistent with the Interim Conunission Policy Statement on.
Technical Specifications. The staff has taken the position thut TS are ree,uired for SB0 response equipment. However, the question of how sptcifications for the SB0 equipment will be applied is currently being considered generically by the NRC in the context of the Technical Specification Improvement Program and remains an open item at this time.
In the interim, the staff expects plant procedures will reflect the appropriate testing and surveillance requirements-to ensure the operability of the necessary SB0 equipment., If the staff later determirm that TS regarding the SB0 equipment'is warranted, the licensee will be notified of the implementation requirements.
l A revised response to the SB0 Rule which addresses the areas of nonconformance should be submitted for staff review within 60 days. Subject to an acceptable resolution of the identified nonconformances, the issue of conformance to,the SB0 Rule remains open for ANO 182.
f J
g Sincerely, g
Oriainal sissed 4:
Theodore R. Quay, Acting Director SO Project Directorate IV-1 Division of Reactor Projects.'III, gr IV, Y and Special Projects y
Office of Nuclear Reactor Regulation U
Enclosures 3
As stated Ob 1
cc t/ enclosures:
See next page G3 o
DISTRIBUTION i
n 6ttfued T. Quay PD4-1 Plant File M. Virgilio MS13E4 NRC FDR L. Berry.
PD4 1 Reading File C. Poslusny
'J Local PDR T. Alexion OGC MS15B18 E. Jordan HNBB'3701 P. Tam MS13H3 ACRS (10) MS P-315
- See Previous Concurrence i
0FC
. :*PD4-1/LA
- PD4-1/PM
- PD4-1/PM
- SELB/ DEST
- PD4-1/D NAME :LBeriy
- TAlexion:1h
- Crosiusny
- FRosa
- TQuay.
DATE :10/02/90
- 10/02/90
-:10/02/90
.:10/03/90:
- 10/10/90-d 0FFICIAL RECORD COPY.
Document Name:
-j" I
- October 10, 1990 DISTRIBUTION Docket File NRC PDR Local PDR PD4-1 Reading M. Virgilio MS 13E4 F. Rosa MS 7E4 P. Tam MS13H3 T. Quay L. Berry C. Poslusny T. Alexion OGC MS15B18 E. Jordan MS MNBB 3701
)
ACRS(10)MSP-315 J
PD4-1 Plant File h
1 4
1 I
- h j
- ,k UNITE D STATES NUCl EAR REGULATORY COMMISSION 3
L i
wAsmuotoN.O c.20555
]
October 10, 1990 Docket Nos. 50-313 l
and 50-368 Mr. Neil S. Carns Vice President, Operations AND Entergy Operations, Inc.
Route 3 Box 137G Russellville, Arkansas 72801
Dear Mr. Carns:
SUBJECT:
SAFETY EVALUATION REPORT FOR THE ARKANSAS NUCLEAR ONE, UNIT NOS. I AND 2 (ANO 1&2) - RESPONSFS TO THE STATION BLACK 0UT RULE (TAC NOS. 68508 AND 68500)
By letters dated April 13.1989, April 3,1990, and July 17, 1990, Arkansas Nuclear One, Unit Nos.1&2 (ANO 1&2)- submitted responses to the Station Blackout (SBO) Rule. These responses were reviewed by an NRC contractor, Science Appl l cations International Corporation (SAIC) and the NRC staff.
Enclosures 1 and 2 are the Safety Evaluation Reports (SERs) addressing the, licensee's responses, and attached to each SER is the associated SAIC Technical-Evaluation Report, in the ANO 1&2 submittals, you proposed using existing Emergency Diesel Generators (EDGs) as an alternate AC (AAC) power source for each unit and have submitted your responses in the $80 generic response format.
Based on our review of the responses, we find that ANO 182 do not conform with the SB0 Rule and the guidance of Regulatory Guide (R.G.) 1.155, NUMARC 87-00 and NUMARC 87-00, *. Supplemental Questions / Answers and Major Assumptions," dated i
December 27,1989 (issued to the industry by NUMARC on January 4,1990). The areas of nonconformance are identified in the enclosed SERs.
It should be noted that the staff has also recently received a submittal dated September 24, 1990, from Entergy Operations, Inc., which provides clarifications and revisions to the previous submittals. We have completed a preliminary-j review of the submittal and have concluded that the information provided does J
not affect the conclusions included in the SERs. The staff will review the September submittal further with your response to this letter.
In addition, the following areas may require follow-up inspection'by the NRC to verify that the implementation of any modifications, and.the supporting documentation which you may propose as a~ result of this evaluation.- are adequate to meet the Station Blackout Rule.
Inspection guidance for this is being developed, a.
Hardware and procedural modifications, j
b.
SB0 procedures in accordance with R.G. 1.155, Position 3.4, and NUMARC 87-00, Section 4, i
c.
Operator staffing and training to follow the identified actions in i
the SB0 procedures, p.
ky
O i
i Neil S. Carns 2
October 10, 1990 i
d.
EDG reliability program meeting, as a minimum, the guidelines of R.G. 1.155, e.
Equipnitnt 6nd components required to cope with an SB0 are incorporated in a QA program that meets the guidance of R.G. 1.155, Apper. dix A, and f.
Actions talen ptrtair.ing to the specific recommendations noted in the SER.
The guidance provided on Technical Specifications (TS) for an SB0 states that the TS should be consistent with the Interim Comission Policy Statement on Technical Specifications. Tho staff has taken the position that 11, u t t eeuired f or SB0 response equipment. However, thf. question cf trw sptcifications for.
the SB0 equipn.ent will be applied is currently being considered generically by-the NRC in the context of the Technical Specification Improvement Program and r emains an open iten. at this time.
In the interim, the staff expects plant-procedures will ref1cct the appropriate testing and surveillance requirements to ensure the operability of the necesscry 500 equipment.
If the staff later cetermines that TS resurcing the SB0 equipmert is warrar.ttd, the licensee will be notiiled of the implementation requirements.
A re'.ista response to the SB0 Pult wfich addresses the areas of nonconformance shoLid be submittec ter staff revient rethin E0 days. Subject to an accepttble resolution of the identified nonconformances, the issue of conformance to the i
5D0 Rule remains open for AhC 1&2.
Sincerely, orisinal sissed tt:
Theodore R. Quay, Acting Director Project Directorate IV.1 Division of Reactor Projects - III, i
IV, V and Special Projects Office of Nuclear Reactor Regulation l
l
Enclosures:
As stated cc w/ enclosures:
See next page O1STRIBUTION bocket File T. Quay PD4-1 Plant F ile M. Virgilio MS13E4 NRC PDR L. Berry PD4 1 Reading File C. Poslusny Local PDR T. Alexion OGC MS15B16 E. Jordan HNBB 3701 P. Tam MS13H3 ACRS(10)MSP-315
- See Previous Concurrence
~
P.I L :*FD4-1/LA
- PD4-1/PM
- PD4-1/PM
- 5ELB/ DEST
- PD4 1/Dn, p.... :................ :.............. :.............. :.............. :........ /.7.... ::...
KAME :LEerty
- 1Aie> ion:1h
- CPosiusny
- FRosa
- TQuay "
DATE
- 10/02/90
- 10/02/90
- 10/02/90
- 10/03/90
- 10/ 't /90 i -
OFFICIAL RECORD COPY Document hame:
F.
~
i Neil S. Carns d.
EDG reliability program meeting, as a minimum, the guidelines of R.G. 1.155, e.
Equipment and components required to cope with an SB0 are incorporated in a QA program that meets the guidance of R.G.1.155 Appendix A, and f.
Actions taken pertaining to the specific recommendations noted in the SER.
TheguidanceprovidedonTechnicalSpecifications(TS)foranSB0statesthat the TS should be consistent with the Interim Commission Policy Statement on Technical Specifications. The staff has taken the position that TS are required for SB0 response equipment. However, the_ question of how-specifications for i
the SB0 equipment will be applied is currently being considered generically by the NRC in the context of the Technical Specification Improvement' Program and 4
I remains an open item at this time.
In the interim, the. staff expects that plant procedures will reflect the appropriate testing and surveillance requirements to ensure the operability of the necessary SB0 equipment.
If the staff later determines that TS regarding the SB0 equipment is warranted, the licensee will be notified of the implementation requirements.
A revised response to the SB0 Rule which addresses the areas'of nonconformance should be submitted for staff review within 60 days. Subject to an acceptable resolution of the identified nonconformances, the. issue of conformance to the SB0 Rule remains open for ANO 1&2.
Sincerely,
- f. tck'.i Ob,f-TheodoreR.Qua}y,ActingDirector-A Project Directorate IV-1.
Division of Reactor Projects
.111,.
IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page
b.
e Entergy Operations, Inc.
Arkansas Nuclear One, Units 1 & 2 cc:
Mr. Early Ewing, General Manager Mr. Donald C. Hintz J
Technical Support and Assessment Executive Vice President Arkansas Nuclear One and Chief Operating Officer Route 3 Box 137G Entergy Operations, Inc.
)
Russellville, Arkansas 72801 P. O. Box 31995 Jackson, Mississippi 39286 Mr. Jerry Yelverton Mr. Gerald Muench Director Nuclear Operations Vice President Operations Support Arkansas Nuclear One Entergy Operations, Inc.
Route 3 Box 137G P. O. Box 31995 1
Russellville, Arkansas 72801 Jackson, Mississippi 39286 Mr. Nicholas S. Reynolds Mr. Robert B. McGehee Bishop, Cook, Purcell & Reynolds Wise, Carter, Child & Caraway 1400 L Street, N.W.
P. O. Box 651 Washington, D.C.
20005-3502 Jackson, Mississippi-39205 Mr. Robert B. Borsum Mr. Charles B. Brinkman, Manager Babcock & Wilcox Washington Nuclear Operations Nuclear Power Generation Division Combustion Engineering, Inc.
1700 Rockville Pike, Suite 525 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Rockville, Maryland 20852 Senior Resident inspector Mr. Tom W. Nickels -
U.S. Nuclear Regulatory Commission Arkansas Nuclear One 1 Nuclear Plant Road Route 3, Box 137G Russellville, Arkansas 72801 Russellville, Arkansas 72801 Regional Administrator, Region IV Admiral Kinnaird R. McKee, USN (Ret)
U.S. Nuclear Regulatory Commission Post Office Box 41-Office of Executive Director Oxford, Maryland 21654 for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 l
Honorable Joe W. Phillips County Judge of Pope County Pope County Courthouse l
Russellville, Arkansas 72801 Ms. Greta Dieus, Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201
_