05000368/LER-2004-003, Regarding Entry Into an Operational Mode Prohibited by Technical Specification Due to Inoperable Pressurizer Proportional Heaters

Regarding Entry Into an Operational Mode Prohibited by Technical Specification Due to Inoperable Pressurizer Proportional Heaters

ML043360174
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/29/2004
From:	James D Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN110402 LER 04-003-00
Download: ML043360174 (8)

LER-2004-003, Regarding Entry Into an Operational Mode Prohibited by Technical Specification Due to Inoperable Pressurizer Proportional Heaters

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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
3682004003R00 - NRC Website

text

,hEntergy Entergy Operations, Inc.

1448 S R. 333 Russeliville, AR 72802 Tel 501 858 5000 2CAN110402 November 29, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Licensee Event Report 50-368/2004-003-00 Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6

Dear Sir or Madam:

In accordance with 10CFR50.73(a)(2)(i)(B), enclosed is the subject report concerning operation in a mode prohibited by technical specifications.

A new commitment contained in this submittal is summarized in Attachment 1.

Sincerely, Dale E. James Manager, Licensing DEJ/fvb Attachment Enclosure 4.11

Ie

- D-

.1
60

2CAN1 10402 Page 2 cc:

Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 LEREventstinpo.org

Attachment I 2CAN 10402 Commitment Summary to 2CAN1 10402 Page 1 of 1 This table identifies actions discussed in this letter which Entergy Operations, Inc.

(Entergy) commits to perform. Any other actions discussed in this submittal are described for the NRC's information and are not commitments.

TYPE SCHEDULED

COMMITMENT

COMPLETION DATE ONE-TIME CONTINUING ACTION COMPLIANCE Replace ANO-2 Prior to the end of the pressurizer proportional next ANO-2 refueling heater power panels X

outage 2PP5 and 2PP6 (Estimated date is 4/1512005)

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

, the NRC may not conduct sfor each block) or sponsor, and a person Is not required to respond to, the Information digits/characters frecblk)Collection.

3. PAGE Arkansas Nuclear One - Unit 2 05000 368 1 OF 4

4. TITLE Entry into an Operational Mode Prohibited by Technical Specification due to Inoperable Pressurizer Proportional Heaters

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE l

8. OTHER FACILITIES INVOLVED SEUNTA RVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 09 29 2004 2004

- 003 -

00 11 29 2004 05000

9. OPE1ATING MODE I.THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b)

D 20.2203(a)(3)(i)

D 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 3 E0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)

D 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) 0o 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)

D 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) 0 20.2203(a)(2)(iii) 0 50.36(c)(2)

D 50.73(a)(2)(v)(A) 0 73.71(a)(4) 0 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 000 0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(a)(2)(vi) 10 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)

SpecifylnAbstractbelow 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)

E.

Safety Significance

The function of the pressurizer proportional heaters is to adjust the heat input as required to compensate for steady state losses and to maintain the desired pressure in the pressurizer. To assure sufficient pressurizer control for natural circulation flow at hot standby conditions following a loss of off-site power, the operator re-energizes the proportional heaters from the diesel generator safety buses; The 150kW capacity powered from an assured power source ensures, considering ambient heat losses, that RCS sub-cooling margin will be maintained greater than or equal to 20 degrees F for a period of 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> following a loss of off-site power. This time period includes a period of one-half hour at the beginning of the transient in which the heaters are unavailable.

The pressurizer heaters are not credited in any accident analysis.. The design supports natural circulation cooldown of the RCS during a loss of off-site power event. Ample time is afforded during the post-trip cooldown phase to establish a backup power supply to one or both banks of proportional heaters. Operation with heater bank output less than 150 kW would only act to decrease the time to reach the 20 degree F margin-to-saturation point or delay the cooldown.

Even with no heater capability, the plant could be cooled down to the shutdown cooling operations window without reaching saturated conditions.

In addition, High Pressure Safety Injection [BQ] feed and bleed may be initiated if saturated conditions are reached to maintain core cooling. Therefore, the safety significance of this condition was determined to be minimal.

F.

Basis for Reportability This report of a condition prohibited by technical specifications is submitted in accordance with 10CFR50.73 (a) (2) (i) (B).

G.

Additional Information

There have been no previous similar events reported by ANO as Licensee Event Reports.

Pressurizer proportional heater circuit breaker panels 2PP5 and 2PP6 are Series 4 panels manufactured by ITE Imperial Corporation.

Energy Industry Identification Systems (EIIS) are identified in the text as [XX].