ML20217N260
| ML20217N260 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/29/1998 |
| From: | Muench R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ET-98-0035, ET-98-35, GL-96-01, GL-96-1, NUDOCS 9805050271 | |
| Download: ML20217N260 (3) | |
Text
_
- - 3 W$LF CREEK
~
NUCLEAR OPERATING CORPORATION Richard A. Muench Vice Prealdent Engineering April 29, 1998 ET 98-0035 U. S. Nuclear Regulatory Commission ATTN:
Documept Control Desk Mail Station P1-137 Washington, D, C.
20555
Reference:
1)
Letter WO 96-0068, dated April 18, 1996, from O.
L.
Letter WO 97-0028, dated February 19, 1997, from C. C.
Subject:
Docket No. 50-482:
Confirmation of Completion of Requested Actions Associated to Generic Letter 96-01,
" Testing of Safety-Related Logic Circuits" Gentlemen:
This letter provides confirmation that Wolf Creek Nuclear Operating Corporation (WCNOC) has performed the activities necessary to satisfy the actions requested by Generic Letter 96-01, as clarified in Reference-1.
These activities were completed on March 31, 1998, consistent with our commitment in
' Reference 2.
WCNOC reviewed logic testing within the scope of.our review to both the current Technical Specifications and the equivalent sections of the Improved Standard Technical Specifications (ISTS).
Current Technical Specification requirements for the Reactor Protection System (RPS),
Emergency Diesel Generator (EDG) and Load Shedder Emergency Load Sequencer (LSELS),
and actuation logic for the Engineered Safety Features (ESP) systems are' contained in the Technical Specifications sections 3.3.1, 3.8.1.1, and 3.3.2 respectively.
For the RPS and ESF logics, current Technical Specifications required ~ testing is bounded by the testing specified in Table 4.3-1 and 4.3-2 (Actuation Logic Test, Trip Actuation Device Operation Test (TADOT), Channel Operational Test, Master Relay Test and Slave Relay Test). The Technical l
Specifications for the EDG were restructured with the issuance of License Amendment 101, dated August 9,
1996.
The numbers reported here are the current numbers.
EDG load shedding and sequencing testing required by current Technical.
Specifications is defined by Surveillance Requirements 4.8.1.1.2g.2),
4.8.1.1.2g.3),
4.8.1.1.2g.4),
4.8.1.1.2g.6),
4.8.1.1.2g.8),
.4.8.1.1.2g.9) and 4.8.1.1.2g.11).
In addition, 4.8.1.1.2g.5) was added to the Generic Letter 96-01 scope of work as it was formally part of renumbered
- 4. 8.1.1. 2g. 6).
The systems and components within the scope of Generic Letter 96-01 are typically identical redundant trains or channels.
Therefore, WCNOC uses essentially identical, but separate, procedures for the redundant train or channel.
For ' the Generic Letter 96-01 review, WCNOC grouped these similar procedures and performed a review of one of the common groups.
If there were differences between the trains or channels, these differences, as a minimum,
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- were reviewed.in the applicable procedure's.
WCNOC recognized that-the ESF andJ LSELS output contacts are used in the control circuits of different components,' depending on the train.
This review included the-output: contact 'of La single strain.
If deficienc' s were noted in a creviewed procedure, then-theLremainder.of the procedures in that group
'were reviewed for existence of-that. deficiency and revised'as necessary to comply Twith the Technical Specifications.
This is consistent with-the NRC-response to ' question #11 - from the.' generic letter workshop held
-March-19,'1996..
Results of the ' Generic Letter- ' review. have been evaluated,- when necessary, in the Corrective -'- Action Program.
'In addition, issues
' determined to be reportable were documented in Licensee Event Report 50-482/97-010.'
As; noted in' Reference - 1, WCNOC took four exceptions to, the generic
' letter guidance.
Wolf Creek ' Generating Station (WCGS)
Technical Specifications are a relatively current version within the industry-and.
were used'to: develop the current surveillance procedures.
The in!,tial development of these procedures occurred in.the early 1980s.to support licensing of the plant, and took advantage of Industry operating Experience at the, time.
Adpitionally, relevant Industry Operating Experiences have been. incorporated in procedure-revisions.
Therefore, as discussed in Reference 1, the following areas have been adequately reviewed:in accordance with the intent of the Generic Letter.
Although a detailed review was not-performed in the following areas, -it. was
- onfirmed that surveillance procedures existed to test these items and
..that test overlap existed from the bistable to the end device.
Westinghouse-7300 Process Instrument Loops RWestinghouse. Solid State Protection System (SSPS) o
. Westinghouse Slave. Relays e
o. Balance of the Plant- (BOP) Engineered _ Safety Features Actuation System (ESFAS) Load Shedder Emergency. Load Sequencer (LSELS).
If you have any questions concerning this response, please contact me at-
~ (316)' 364-88 31, extension 4034i or Mr. Micha el - ' J.. Angus, at extension 4077.
Very truly yours, Richa d A. Muench RAM /rir ec:
E D. Johnson (NRC)
- 2. N. Merschoff'(NRC)
.J.
F.-Ringwald (NRC)
K. M. Thomas ~(NRC) o b-e s-
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(Richard-A. Muench,'of lawful age,.being first= duly sworn upon oath'says that heis'Vice President Engineering of Wolf Creek Nuclear Operating Corporations.
'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.
6 power and~ authority to do so; and.that the, facts.therein stated'are true and
.-correct'to the best of his.knowledgei informstion and belief.
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'By
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~RichardA.fiuench Vice President ~
Engineering.
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SUBSCRIBED and sworn to before me this day.of
, 1998'.
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