ML20082D937
| ML20082D937 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/06/1995 |
| From: | Johannes R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20082D938 | List: |
| References | |
| CO-95-0032, CO-95-32, NUDOCS 9504110040 | |
| Download: ML20082D937 (5) | |
Text
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a-W$LF CREEK NUCLEAR OPERATING CORPORATION Rchard N. Johannes Ctuef Adrmrustratwo Offcer April 6, 1995 CO 95-0032 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.
C.
20555
Reference:
Letter NA 94-0089, dated May 24, 1994, from R.
C.
Subject:
Docket. No. 50-482:
Revision to Technical Specifications Based on NRC Final Policy Statement on Technical Specifications Improvements; Revisions Gentlemen:
This letter transmits revisions to the application for amendment to Facility Operating License No. NPF-42 for Wolf Creek Generating Station (WCGS) dated May 24, 1994.
The Reference proposed modifications to the WCGS Technical Specifications to incorporate improvements in scope and centent endorsed by the Nuclear. Regulatory Commission in its Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors 59 FR 39132, dated July 22, 1993.
These revisions to the Reference are being submitted due - to discussions held on January 31, 1995, with Mr.
W.
D.
Reckley, NRC Project Manager. Based upon these discussions, in part, Technical Specification 3/4.4.5,
" Steam Generators," and its associated Bases section will be retained in the technical specifications with no proposed revisions.
Attachment I provides a revised page from the original Safety. Evaluation.
Attachment II _ consists of the revised Technical Specification pages and Attachment III provides revised pages from the application of the Policy Statement criteria to the WCGS Technical Specifications.
The revised Technical Specification pages associated with the retention of Technical - Specification 3/4.4.5 and its associated Bases section have not been included in Attachment II These proposed revisions to the Reference have no affect. on the conclusions of the previous Safety Evaluation, No Significant Hazards Consideration Determination, nor Environmental Impact Determination.
A copy of this revision, with attachments, is being provided to the designated Ir Kansas State official.
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$0 I P.O. Box 411/ Burlington, KS 66839 / Phone: (316) 364-8831 o h82 An Equal opportunny Employer M/F/HCNET PR D
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CO 95-0032 l5
'Page 2'of 2 i
If you ' : have.~any. questions concerning this matter, -please _ contact me.at
.(316) 364-88314 extension 4001, or Mr. Richard D Flannigan, at extension 4500.
.s very truly yours, WY s
-I Richard N. Joha es
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RNJ/jra Attachments:
I.- Revised Safety Evaluation Page II - Revised Technical Specification Pages III - Revised Pages from the Application of the Policy-Statement criteria to the Technical Specification cc:
G.
W. Allen (KDHE), w/a L. J.
Callan (NRC), w/a D. F. Kirsch (NRC), w/a W. D. Reckley (NRC), w/a j
J. F. Ringwald (NRC), w/a i!
J. C. Stone (NRC),. w/a
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. STATE OF KANSAS-
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Richard N. Johannes, of lawful age, being first duly sworn upon oath says that' he is Chief Administrative. Officer.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 his knowledge, information and belief.
N ry Pub 5: ba Pan as 8Y
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' y Appt. Expires T-31-98 Rfchard N. Johannes.,
M Chief Administrativ. Officer 5dc day of 4d
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SUBSCRIBED and sworn to before me this A
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ary Public' Expiration Date
Attachment I to CO 95-0032 Page 1 of 2 ATTACHMENT I REVISED SAFETY EVALUATION PAGE J
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Attachment I to NA 94-0089 Page 10 of 11 i
New Action d applies when two hydrogen monitor channels are inoperable, i
requiring the restoration of one hydrogen monitor channel to O?ERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time is reasonable based on the I
backup capability of the Post Accident Sampling System to monitor the hydrogen concentration for evaluation of core damage and to provide information for operator decisions.
Also, it is unlikely that a LOCA (which would cause core damage) would occur during this time. Consistent with the new Standard Technical Specifications, NUREG 1431, LCO 3.6.4.1 is deleted since LCO 3.3.3.6 contains the appropriate actions and surveillances.
1 PORV and PORV bicck velve pcaitica indicatsr; havc bcca deletw+frem-Technical.
.spee444 :tica 2.? J.f.
Lee: Of poskt4 n indic:tient requ4ree-that th: 7,ction;
- irted eith ' ; -3. { t be entered; ther:fere, there is ne need te-01:0 h:
the;c indicaters-under 1,00 0.3.0.0.
It i; furthcr noted that thc;c indicatcrc er: net ?jp:
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c richic: :: Wolf Orcck, nor arc thcy RC 1.07 Cete,erf 1.
Men;.hly channci check; for thc;c indicetcro have bcen addcd as OR 4.0.4.0 and i
DETERMINATION OF NO UNREVIEWED SAFETY OUESTIOR The proposed changes to the Technical Specifications do not involve an unreviewed safety question because the operation of the WCGS in accordance
~
with these proposed changes would not.
(1)
Involve an increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important-to safety previously evaluated in the USAR. Overall protection system performance will remain within the bounds of the accident analyses documented in i
USAR Chapter 15, WCAP-10961-P, and WCAP-11883, since no hardware changes are proposed.
There will be no effect on these analyses, or any other accident analysis, since the analysis assumptions are unaffected and remain the same as discussed in the USAR.
Safety-related equipment will continue to function in a manner consistent with the above analysis assumptions and the plar.t design i
t basis.
As such, there will be no degradation in the performance of nor an increase in the number of challenges to equipment assumed to function
{
during an accident situation.
These Technical Specification revisions do not involve any hardware changes nor do they affect the probability of any event initiators.
There will be no change to normal plant operating parameters, ESFAS actuation setpoints, accident mitigation capabilities, accident analysic assumptions or inputs.
These changes are administrative in nature, in
]
that they relocate those requirements not important to accident prevention or mitigation from the Technical Specifications to USAR Chapter 16.
Therefore, these changes will not increase the probability or consequences of an accident or malfunction.
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