05000302/LER-2004-004, Regarding NUREG-1022 Clarification Required Reporting of Previous Steam Generator Tube Inspection Results

Regarding NUREG-1022 Clarification Required Reporting of Previous Steam Generator Tube Inspection Results

ML043340228
Person / Time
Site:	Crystal River
Issue date:	11/22/2004
From:	Franke J Progress Energy Florida
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F1104-03, NUREG-1022 LER 04-004-00
Download: ML043340228 (8)

LER-2004-004, Regarding NUREG-1022 Clarification Required Reporting of Previous Steam Generator Tube Inspection Results

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3022004004R00 - NRC Website

text

a Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating license No. DPR-72 Ref: 10 CFR 50.73 November 22, 2004 3F1 104-03 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

LICENSEE EVENT REPORT 50-302/2004-004-00

Dear Sir:

Please find enclosed Licensee Event Report (LER) 50-302/2004-004-00. The LER discusses a Notice of Clarification issued by the NRC regarding Steam Generator Tube Integrity Event Reporting Guidelines for NUREG-1022, "Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73," which directed licensees to consider the results of the previous steam generator tube inspections against the NUREG-1022 revised guidelines. Crystal River Unit 3 determined that the as-found steam generator projected leakage value for Steam Line Break, which exceeded the leak rate limit for Refueling Outage 13 (13R), is reportable per the revised NUREG-1022 guidance. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(ii)(A).

No regulatory commitments are made in this letter.

If you have any questions regarding this submittal, please Licensing and Regulatory Programs at (352) 563-4883.

contact Mr. Sid Powell, Supervisor, Si]

Xon A. Franke Plant General Manager Crystal River Nuclear Plant JAFIlvc Enclosure xc:

NRR Project Manager Regional Administrator, Region II Senior Resident Inspector

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Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0613012007 (6-2004)

, the NRC digits/characters for each block) may not conduct or sponsor, and a person is not required to respond to, the Information collection.

3. PAGE CRYSTAL RIVER UNIT 3 05000302 1 OF 7

4. TITLE NUREG-1022 Clarification Required Reporting of Previous Steam Generator Tube Inspection Results

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED S

U1RFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR S

EQUENTIAL R

MONTH DAY YEAR N/A 05000 FACILITY NAME DOCKET NUMBER 09 24 2004 2004 - 004 - 00 11 22 2004 N/A 05000

9. OPERATING MODE

.THISREPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check a)that apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A)

O 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)

10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) o 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71 (a)(4) o 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 100%

0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)

Specify in Abstract below or In (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (if more space Is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)

ATTACHMENT 2 LIST OF COMMITMENTS The following table identifies those actions committed to by PEF in this document. Any other actions discussed in the submittal represent intended or planned actions by PEF. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Supervisor, Licensing & Regulatory Programs of any questions regarding this document or any associated regulatory commitments.

COMMITMENT

DUE DATE SECTION No regulatory commitments are being made in this submittal.