05000440/LER-2007-001, From Perry Regarding Automatic Reactor Protection System Actuation Due to Reactor Coolant Level Decrease

From Perry Regarding Automatic Reactor Protection System Actuation Due to Reactor Coolant Level Decrease

ML072050321
Person / Time
Site:	Perry
Issue date:	07/16/2007
From:	Allen B FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PY-CEI/NRR-3047L LER 07-001-00
Download: ML072050321 (5)

LER-2007-001, From Perry Regarding Automatic Reactor Protection System Actuation Due to Reactor Coolant Level Decrease

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii) 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
4402007001R00 - NRC Website

text

FENOC FirstEnergy Nuclear Operating Company Perry Nuclear Power Station 10 Center Road Perry, Ohio 44081 Barry S. Allen Vice President 440-280-5382 Fax: 440-280-8029 July 16, 2007 PY-CEI/NRR-3047L United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Perry Nuclear Power Plant Docket No. 50-440 Ladies and Gentlemen:

Enclosed is Licensee Event Report (LER) 2007-001, "Automatic Reactor Protection System Actuation Due To Reactor Coolant Level Decrease."

There are no regulatory commitments contained in this letter or its enclosure. Any actions discussed in this document that represent intended or planned actions are described for the NRC's information, and not regulatory commitments.

If there are any questions conceming this matter, please contact Mr. Jeffrey J. Lausberg, Manager Regulatory Compliance, at (440) 280-5940.

Very truly yours, Barry S. Allen Enclosure: LER 2007-001 cc:

NRC Project Manager NRC Resident Inspector NRC Region III

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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 6/30/2007 (6-2004)

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE Perry Nuclear Power Plant 05000440 1 OF4

4. TITLE Automatic Reactor Protection System Actuation Due To Reactor Coolant Level Decrease

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR I SEQUENTIAL REV I MONTH DAY YEAR I FACILITY NAME I DOCKET NUMBER I

NUMBER NO.

I I

I 05 15 2007 2007 -

001 000 07 16 2007 FACILITY NAME DOCKET NUMBER

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1D 20.2201(b)

El 20.2203(a)(3)(i)

EL 50.73(a)(2)(i)(C)

El 50.73(a)(2)(vii)

El 20.2201(d)

EL 20.2203(a)(3)(ii)

EL 50.73(a)(2)(ii)(a)

EL 50.73(a)(2)(viii)(A)

EL 20.2203(a)(1)

EL 20.2203(a)(4)

EL 50.73(a)(2)(ii)(B)

EL 50.73(a)(2)(viii)(B)

[I 20.2203(a)(2)(i)

EL 50.36(c)(1)(i)(A)

EL 50.73(a)(2)(iii)

EL 50.73(a)(2)(ix)(A)

EL 20.2203(a)(2)(ii)

EL 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A)

LI 50.73(a)(2)(x)

10. POWER LEVEL El 20.2203(a)(2)(iii)

EL 50.36(c)(2)

[] 50.73(a)(2)(v)(A)

LI 73.71(a)(4) 31 EL 20.2203(a)(2)(iv)

LI 50.46(a)(3)(ii)

LI 50.73(a)(2)(v)(B)

LI 73.71(a)(5)

LI 20.2203(a)(2)(v)

[j 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

E] OTHER LI 20.2203(a)(2)(vi)

[L 50.73(a)(2)(i)(B)

LI 50.73(a)(2)(v)(D)

Specify in Abstract below I_

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 NRC Form 366A)

Procedure PAP-1 107, "Temporary Instruction Control," will be changed to include clear TXI entry and exit, suspension, and termination criteria. It will define the expected organizational response for unexpected test results or unexpected transients during a TXI. The procedure will require a brief at the start of each shift or procedure section. This action is currently scheduled for completion in October, 2007.

A "Conduct of Test" procedure will be created based upon, and aligned with, best industry practices in order to increase the formality and quality of testing. Testing criteria will include clear roles and responsibilities of each test participant, termination criteria, and expected responses to unexpected results. Lessons learned from this event will be communicated to site supervision. These actions are currently scheduled for completion in October, 2007.

FENOC Project Management will review FENOC processes/procedures to ensure that any FENOC projects for digital controls have the correct standards and durations established for testing. This action is currently scheduled for completion in October, 2007.

PREVIOUS SIMILAR EVENTS

A review of Licensee Event Reports (LER) over the past 3 years did not identify any previous similar events. A review of corrective action documents over this time period concludes that no condition reports were found relevant to the failure mechanisms, which defined this event.

COMMITMENTS

There are no regulatory commitments contained in this report. Actions described in this document represent intended or planned actions, are described for the NRC's information, and are not regulatory

commitments

Note: Although this LER has been reviewed and approved by site management, the associated condition report's root cause evaluation is expected to receive an internal "collegial" review by the site's corrective action review board after the LER has been submitted to the NRC.