ML20205A196
| ML20205A196 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/25/1999 |
| From: | Muench R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20205A200 | List: |
| References | |
| ET-99-0015, ET-99-15, NUDOCS 9903300324 | |
| Download: ML20205A196 (5) | |
Text
n-WapLF CREEK NUCLEAR OPERATING CORPORATION Richard A. Muench Vice President Engineering MAR 2 51999 ET.99-0015 U. S. Nuclear Regulatory Commission ATTN:
Document,. Control Desk Mail Station.Pl-137-Washington, D. C.
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Reference:
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Letter" ET 97-0050, -dated May
'15, 1997, from R.
A.
2). Letter ET 99-0009, dated March 5,
1999, from R.
A.
Subject:
-Docket No.
50-482:
Technical Specification Conversion Application - Supplement 2 Gentlemen:
Pursuant to 10CFR50.90, Wolf Creek Nuclear Operating Corporation (WCNOC) requested an amendment to the Wolf Creek Generating Station (WCGS) operating license by incorporating changes to the WCGS Technical Specifications as provided in Reference 1 and as supplemented by Reference 2.
WCNOC hereby provides a second supplement to the request provided in Reference 1.
This supplement provides' changes based on discussions with the NRC reviewers between March 10 and March 19, 1999.
Enclosed is the additional information or supporting documentation for the proposed changes.
The appropriate mark-ups of the current Technical Specifications and-improved _ Technical Specifications the description of the change to the current Technical Specifications and improved Standard Technical Specification,.and the proposed "No Significant Hazards Consideration Determination," are enclosed.
In accordance with CFR 50.91(b), WCNOC is providing the State of Kansas:with a copy of this supplement.
-If you have any questions concerning this response, please contact me at (316) 364-4034, or Mr. Michael J. Angus, 316-354-4077.
Very truly yours,
~
9903300324 990325
/
PDR ADOCK 05000482
' W P
PDR Rich d A. Muench RAM /rir-
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Attachment Enclosure cc:
V. L. Cooper (KDHE), - w/a W. D. Johnson (NRC), w/a E. W. Merschoff (NRC), w/a Senior Resident Inspector (NRC), w/a K. M. Thomas-(NRC), w/a PO. Box 411 / Burhngton, KS 66839 / Phone: (316) 364-8831 An Equal Opportunity Employer M F/HCNET L,,..
l STATE OF KANSAS
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SS COUNTY OF COFFEY
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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 au'.hority to do so; and that the facts therein stated are true and
. correct to the best of his knowledge, information and belief.
By
/[j4 Richard [.Muench Vice President Engineering SUBSCRIBED and sworn to before me this day of bd./16
, 1999..
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N10MlE L, m Of7/IA r_
8/ 88Ad gg g 6-//-/)MS Notary Public Expiration Date -
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ADDITIONAL INFORMATiON COVER SHEET l'
l ADDITIONAL INFORMATION NO: O 3.3-21 APPLICABILITY: WC REQUEST:
ITS 3.3.3 was revised to reflect current TS 3.3.3.6. containment isolation valve l
position (and Notes) and condensate storage tank level were deleted.
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[ Combined the power and source range neutron flux entries into a single neutron l
flux entry.] Consolidated the thermocouple / core cooling detection system entries.
l Changed number of required channels for RCS temperature to 2 for both hot and cold leg temperature. Changed containment pressure wide range to containment pressure normal range and added refueling water storage tank level, steam line pressure, and SG water level (Narrow Range) functions as these are current TS requirements. Changed the required number of channels for SG water level (Wide Range) and AFW f:ow rate from 2 per SG to 1 per SG and added corresponding notes to Conditions A and C.
Comment:
(1) ITS includes thermocouples as PAM instrument functions without specifying the number required to be operable. Provide a revised table entry for funciton
- 15. Include the appropriate discussion of change. {WC}
(2) Provide a table footnote to specify the need for the operable instruments to be in the same coolant bop. Provide a Bases discussion of the proposed footnote. {WC}
l (3) Correct the table entry making it based on each core quadrant as a table function.
The Bases Actions in WC already specify the quadrant basis. CW may need to make conforming Bases changes. {WC & CW}.
(4) Revise ITS Conditions A & C Notes pertaining to AFW and SG water level inoperable channels. Two instrumented SGs are required to be operable to coaduct a plant shutdown. Thus, the LCO is 1 channel each of AFW and wide range level per SG.
The staff does not credit AFW as diverse to Level which means one inoperable AFW or Level channel in a SG results in loss of the PAM monitoring function for that SG.
l Therefore, Conditons are entered when less than 2 SGs have both AFW and wide range level channel operable. Condition A for AFW and wide range level functions should allow a 30 day Completion Ene for one or more inoperable AFW or Level channels in one, two or three SGs. Condition C for AFW or wide range level functions should allow a 7 day Completion for one or more inoperable AFW or Level channels in each SG.
FLOG RESPONSE: (original)(1) This comment is applicable to Wolf Creek only. The ITS markup has been corrected to reflect the Required Channels as "2*/ core quadrant" consistent with the CTS.
(2) This comment is applicable to Wolf Creek and Callaway. It is assumed that this comment is referring to Table 3.3.3-1, Functions 2 and 3 (RCS Hot and Cold Leg Temperature (Wide Range)) and the deletion of the "per loop" in the Required Channels column. The "per loop" was l
deleted based on the plant design of one hot leg temperature indicator (wide range) and one cold leg temperature indicator (wide range) in RCS
' loops 1 and 2. Attached are pages from USAR/FSAR Tabo 7A-3 (Data Sheets 2.1 and 2.2) that indicate the plant design provisions. This change is consistent with CTS Table 3.3-10.
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l l-(3). See the response to item 1 for correcting ITS Table 3.3.3-1 for Wolf Creek. The Wolf Creek and Callaway Bases both state: "When the
. Required Channels in Table 3.3.3-1 are specified on a per SG or per core quadrant basis, then the Condition may be entered separately for each SG or core quadrant, as appropriate. No changes to the ITS Bases are I
necessary.
(4).There is one wide range water level indicator for each steam generator (AE-Ll-0501 through -0504 in the main control room). Diverse indications are available from four narrow range level indicators for each SG when on scale and one AFW flow indicator per SG as discussed in USAR/FSAR Table 7A-3, Data Sheet 4.1. Reactor coolant pressure and reactor coolant temperature indications are also diverse variables from the aspect that they can be used to determine whether adequate core cooling is provided in the absence of wide range level indication on a steam generator. Additional heat sink status diversity is also provided by three steamline pressure indicators perloop. There is one AFW flow rate Indicator for each SG (AL-FI-0001 A through -004A in the main control room). Although not required for Regulatory Guide 1.97 Category 2 variables, diverse indications are available from one wide range level indicator and four narrow range level indicators per SG. As discussed in Table 7A-3, Data Sheet 5.1, each of these four flow indicators is powered by a different separation group. Since only two of four SGs are required to establish a heat sink for the RCS, flow indication to at least two intact SGs is assured even if a single failure is assumed. Section 22 of the Safety Evaluation Report, NUREG-0830 for Callaway and NUREG-0881 for Wolf Creek, specifically accepted the response to NUREG-0737 Item ll.E.1.2 Part 2 for AFW flow rate indication and the CTS, as originally issued did not "AND" wide range level with AFW flow rate as discussed in the comment. Table 7A-3, Data Sheets 4.1 and 5.1 have beers attached to this response for information. The proposed ITS mark-ups maintain the CTS 3.3.3.6 requirements.
(5) ltem 5 is a new item applicable only to Wolf Creek that was discussed during the Section 3.3 meeting held the week of August 11,1998. This item is to revise Table 3.3.3-1 Function 1, Power Range Neutron Flux and Function 2, Source Range Neutron Flux, into one Function, Neutron Flux.
Neutron Flux indication is provided to verify reactor shutdown over the full range of flux that may occur post-accident. One channel of the Gamma-5 Metric neutron flux monitoring system provides scurce range (0.1 to 10 cps) and wide range (10~8to 200% power)in the control room. The second channel provides source and wide range indication at the auxiliary shutdown panel, as well as a two-pen indicating recorder (SE-NIR-0061) for both source and wide ranges in the control room. Neutron flux is used for accident diagnosis, verification of subciiticality, and diagnosis of positive reactivity insertion. The Neutron Flux function was added to CTS 3/4.3.3.6 by Amendment No. 89. Therefore, changing the Function to Neutron Flux is consistent with the plant design and the CTS.
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FLOG RESPONSE: (supplement) As discussed with the NRC reviewer on February 17, 1999, ITS 3.3.3 and associated Bases are revised. Conditions A and C are revised to delete specific reference to the SG Water Level (Wide Range) and AFW Flow Rate Functions. Table 3.3.3-1 is revised for these two Functions to indicate that the Required Channels is 4 (i.e., one per SG). Additionally, in Table 3.3.3-1, the Core Exit Temperature Functions are restored instead of specifying the Thermocouple / Core Cooling Detection System.
FLOG RESPONSE: (supplement) As discussed with the NRC reviewer on March 12,1999, additional changes are made to resolve editorial / consistency comments provided by the reviewer.
ATTACHED PAGES:
Attachment No. 9, CTS 3/4.3 - ITS 3.3 Encl. 5B B 3.3-150, B 3.3-152 I
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