ML20217N188
| ML20217N188 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/31/1998 |
| From: | Muench R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ET-98-0025, ET-98-25, NUDOCS 9804090039 | |
| Download: ML20217N188 (4) | |
Text
.
W$LF CREEK i
NUCLEAR OPERATING CORPORATION j
Richard A. Muench 1
Vice President Engineering March 31, 1998 ET 98-0025 l
U.
S.
Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Station Pl-137 Washington, D. C.
20555
Reference:
Letter WM 97-0009, dated February 7,
- 1997, from O.
L.
Subject:
Docket No.
50-482:
Supplemental Information to the
" Response to ' Request for Information Pursuant to 10 CFR 50.54(f) Regarding Adequacy and Availability of Design Bases Information'"
Gentlemen:
This letter transmits a clarification to information provided in the i
reference.
During a self assessment associated to design bases, the referenced letter was reviewed. As a result of that review, it was noted that
]
information provided associated to the Ir.aervice Testing (IST) Frogram could be misinterpreted.
The confusion was. introduced by the title of the IST document, "IST Design Basis Document."
If the paragraph in question is read as stated, it could lead a reviewer to believe that the IST document contains design bases information, when in reality this document only references the design bases documents.
Tharefore, the paragraph is being revised.
In addition, a typographical error in a reference is being corrected.
The attachment to this letter provides revised text from the original submittal.
Changes have been indicated with a revision bar in the right margin.
If you have any questions concerning this matter, please contact me at (316) 364-8831, extension 4034, or Mr. Michael J. Angus, at extension 4077.
Very truly yours, Y 006 Richa.d A. Muench Attachment
-RAM /jad
\\g cc:
W.
D. Johnson (NRC), w/a
\\A E. W. Merschoff (NRC), w/a J.
F.
Ringwald (NRC), w/a I
X. M. Thomas (NRC), w/a f
9804090039 980331 PDR ADOCK 05000482
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PDR PO. Box 411/ Burlington, KS 66839 / Phone: (316) 364-8831 An Equal Opponunity Ernployer MT/HCNET
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ss Cotnrry or Coryzy
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Richard A. Muench, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he'has read the foregoing document and knows the content thereof; that he-has executed that same for and on behalf of said Corporation with full power and authority to do so; and.that the facts therein stated are true and correct to the best of nis knowledge, information and belief.
By fakt Richard. Muench' Vice Pr sident Engineering-SUBSCRIBEDand'sworntobeforemethish) day of f(/), 1998.
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JULIE A. DALE Nota ublic j
NotalyPLMc ytaleplKapses A Appt, Empiru /O/,20/QP j
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c-Attachment to ET 98-0025 Page 1 of 2
,The information below was located on page on page 15 of 41 of the Attachment to WM 97-0009, " Response to ' Request for Information Pursuant to 10 CFR 50.54(f) Regarding Adequacy and Availability of Design Bases Information'" dated February 7, 1997, from O. L. Maynard to the USNRC.
II.D.3.
Intervice Testing Procedures (IST)
This set of procedures includes IST pump and valve testing and leak rate 3
testing that are based on Technical Specification requirements, ASME code, and 10 CFR 50 Appendix J requirements.
It also includes HVAC testing, heat exchanger testing, and other industry standard testing.
This latter group of testing is based on approved design documents, USAR parameters, or Safety Accident parameters as applicable.
In 1990, the IST procedures were transferred to engineering.
At approximately the same time, a technical review in the for.n of a self assessment and general upgrade of the procedures were initiated. The IST procedures were revised to consider the requirements of Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs" and ASME OM-10, " Inservice Testing of Valves in Light. Water Reactor Power Plants."
The technical review of the IST procedures included the creation of an "IST Design Basis Document."
The "IST Design Basis Document" is a document consisting of reference information that may be used as a tool'to assist a reviewer in identifying documents that contain design bases information.
In addition to the design bases review, the review of changes to an IST procedure by the IST Engineer is administrative 1y required during the procedure change review process to check.that requirements are properly implemented.
The information j
contained in the "IST Design Basis Document," ASME Code and NUREG 1482, l
" Guidelines for Inservice Testing at Nuclear Power Plants," is consulted during the review process for the translation into the procedure.
l i
i i
1 Attachment to ET 98-0025 Page 2 of 2 l
.The bblleted information below was located on page 2 of 2 of the Enclosure to WM 97-0009 and on page 39 of 41 of the Attachment to the same, i
e Conversion to Improved Standard Technical Specifications.
(Letter WO 95-0181, dated December 13, 1995, from O.
L.
Response to Generic Letter 96-01.
(Letter WO 96-0068, dated April 18, 1996, from O. L. Maynard, W3NOC, to USNRC)
Engineering Work Product Evaluations (Letter WM 96-0081, dated July 31, l 1996, from N.
Safety System Functional Assessments (Auxiliary Feedwater, Essential Service Water, Component Cooling Water and Residual Heat Removal) to confirm that no potentially safety / operationally significant design concerns exist.
(Letters WM 96-0081, dated July 31,
- 1996, from N.
S. Carns, WCNOC, to USNRC; WO 96-0101, dated July 3,
- 1996, from O. L. Maynard, WCNOC, to USNRC; and WO 96-0118, dated August 22, 1996, from C. C. Warren, WCNOC, to USNRC)
Non-Safety System Assessments (Feedwater, Service Water, Main Turbine and Main Generation System) to confirm design changes were adequately tested, that those changes were correctly considered in vendor manuals, drawings, spare parts, and procurement documents. (Letters WO 96-0101, dated July 3, 1996, from O.
L. Maynard, WCNOC, to USNRC; and WO 96-0118, i
dated August 22, 1996, from C.
Updated Safety Analysis Report Review Program.
(Letter ET 97-0010, dated February 7, 1997, from R. A. Muench, WCNOC, to USNRC)