ML18152B114

LER 88-028-00:on 880801,spent Fuel Assembly Placed in Wrong Location Due to Inadequate Procedure.Fuel Assembly Was Transferred to Region Ii.Other Assemblies Reviewed to Verify Compliance W/Tech Specs.W/880830 Ltr

ML18152B114
Person / Time
Site:	Surry
Issue date:	08/30/1988
From:	BENSON D L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-042, 88-42, LER-88-028, LER-88-28, NUDOCS 8809060240
Download: ML18152B114 (4)

Text

POW 28-06-01 NRC Form 366 fg.a:, *. i i LICENSEE EVENT REPORT (LER) U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB. NO. 3160-0104 EXPIRES: 8/31/88 Surry Power Station, Unit 1 l DOCKET NUMBER (21 I PAGE 131 O 15 IO IO IO 12 18 IO 1 loFio I 3 FACILITY NAME 111 TITLE (41 Spent Fuel Assembly Placed in Wrong Location Due To lnadeauate Procedure EVENT DATE (51 LER NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED (Bl MONTH DAY YEAR YEAR ;J) SE~~~~i~AL Jt MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(Sl 0 18 Ol 1 8 8 Bl 8 o I 2j a -o Io o 1s 3 Io s1 s OPERATING MODE (91 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock ono or moro of tho folloV(ing)

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--20.405(*1111 M 50,73laH211iiil 50.73(all211xl LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 8 I O 14 3 I 51 71-I 3 I 1 18 14 CAUSE SYSTEM COMPONENT I I I. I I I I I COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC, TURER I I I I I I R ~6 o~;:giE !!l!i!!!ii!!!ii!i!ii!!iii!!ii!i!i!i!i!!!i!l!i!i!J!i::

CAUSE :i!l!ii!!!!i!i!!!!!J:i!!!i!l!!!iiiii!!!i!i!lii!i:jjjj SYS!EM I I COMPONENT MANUFAC-TURER I I I. I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (141 MONTH DAY YEAR EXPECTED SUBMISSION n YES (If yos, complot* EXPECTED SUBMISSION DA TE) NO DATE (151 I I ABSTRACT (Limit to 1400 spt11:os, i.* .. approxim*ts/y fifteon single-spec*

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/inos/ (181 NRC Form 388 19-831 On August 1, 1988 at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br /> with. Unit 1 at 100% power and* Unit 2 at 90% power, during a review of fuel ~ssemblies to be loaded into a dry cask, it was discovered that fue*1 assembly ,, P-29, located in Region I of the spent fuel pool did not meet the storage criteria for Region I. Further investigation determined that the fuel assembly had been in Region I since May 17, 1986. While it had decayed in excess of 150 days, assembly P-29 was not within the acceptable limits of Technical Specification (T. S.) figure 5.4.1. Assembly P-29 had originally been placed in Region II of the spent fuel pool after its discharge from the core in 1977. However, during preparation for ultrasonic testing of other fuel assemblies, in May, 1986, P-29 was relocated to Region I to facilitate the setup of the test equipment.

The cause of the event was due to deficiencies in the method used when spent fuel movement was initiated and directed by on site personnei.

The mispositioned fuel assembly, P-29', was transferred to Region II. All other fuel assemblies stored in Region I were reviewed to verify that they were in compliance with Technical Specification figure 5.4-1. A procedure will be generated to enhance the review of proposed spent fuel assembly movement in the spent fuel pool. 8:3(>'?060240 PDR ADOCJ< ..... . ::, :=:::::(>8:3l) 0~50002:::()

PDC I NRC Form 366A, (913) F>\CILITY NAME (1) ' .*. LICENSEE EV REPORT (LERI TEXT CONTINUAT DOCKET NUMBER (2) POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 LEA NUMBER (6) PAGE (31 Surry Power Station, Unit 1 0 5 0 0 0 2 8 0 8 8 -0 2 8 -0 0 0 2 OF O 3 TEXT (If more spece is required, use additional NRC Form 366A 's/ (17) NRC FORM 3e8A (9-83) 1.0 Description of the Event On August 1, 1988 at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br /> with Unit 1 at 100% power and Unit 2 at 90% power, during a review of fuel assemblies to be loaded into a dry cask, it was discovered that fuel assembly P-29, located in Region I of the spent fuel poo.l {EIIS-ND}, did not meet the storage criteria for Region I. The spent fuel pool is* divided into a two region storage pool, Region I and II. Region I comprises the first three rows of fuel racks adjacent to the fuel building trolley load block. Further investigation determined that the fuel assembly had been in Region I since May 17, 1986. Technical Specification (T. S.) 5.4B states that during spent fuel 9ask handling, Region I is restricted to storage of as~embli~s that have decayed at least 150 days after discharge from the core and whose original e~richment was within the acceptable limits of T. s. figure 5.4-1. While it had* decayed in exces*s of 150 days_., assembly p-*2 9 was not within the acceptable limits* of T. s. figure 5.4.1. 2.0 Safety consequences and Implications The Region I criteria is based on the spent fuel cask drop analysis.

An eva:luation has determined that the misplacement of assembly P-29 in Region I did nqt violate the Keff limit o*f . 95 for the cask drop accident analysis*.

This was -based on the fact that *the magnitude of the reactivity change added by*P-29 assembly was negligible compared to the original model conservatisms and uncertainties.

Therefore, the health and safety of the public were not affected.

3.0 Cause

Assembly P-29 had originally been placed in Region II of the spent fuel pool after its discharge from the core in 1977. However, during preparation for ultrasonic testing of other fuel assemblies, in May, 1986, P-29 was relocated to Region I to facilita~e the setup of the test equipment.

• u.s. GPO, 1988-520-589100070 NRC Form 366A (9-83) * .i FfCILITY NAME (1) *,'. LICENSEE EV , REPORT (LER) TEXT CONTINUAT POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: B/31/88 DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) YEAR :ft SE~~t~11if-L

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Surry Power Station, Unit i 0 5 0 0 0 2 8 0 8 8 -0 2 8 -0 0 0 3 OF O 3 TEXT //f more space is requirtJd, use additional NRC Form 366A's) (17) NRC FORM 366A (9-83) Scheduled movement of fuel is usually directed by the corporate office. This direction for fuel movement takes into consideration, among other factors, Region I storage criteria.

However, since the relocation of P-29 was unscheduled and originated on site, a different method was used. When fuel is moved by the onsite method, a report is generated describing the fuel movement and is reviewed prior to moving the fuel. This review did not verify that the assemblies relocated, met the criteria of Region I. In addition, at the time P-29 was relocated, no cask handling in the spent fuel pool was scheduled, therefore, the restricted criteria of placing assemblies in Region I were not applicable.

Following the relocation of the fuel, the report was transmitted to the corporate offices, where it was reviewed and recorded.

The review did not. verify that .the fuel relocated met. Region I criteria.

Therefore,*

the cause of the event was due-to deficiencies in the methods used when spent fuel movement was initiated and directed by on.site personnel.

4.0 Immediate

Corrective Action(s)

The mispositioned fuel assembly, P-29, was transferred to Region II. All other fuel assemblies stored in Region I were reviewed to verify that they were in compliance with Technical Speqification figure 5.4-1. 5.0 Additional Corrective Action(s)

None required.

6.0 Action(s)

Taken to Prevent Recurrence A procedure will be generated to enhance the review of proposed spent fuel assembly movement in the spent fuel pool. 7.0 Similar Events None. 8.0 Manufacturer/Model Number N/A * *U.S. GPO, 1988-520-589,00070 .I

.,,. \.: I

• August 30, 1988 U.S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C~ 20555 Gentlemen:

• VIRGINIA ELECTRIC ANO POWER COMPANY Surry Power Station P. 0. Box 315 Surry, Virginia 23883 Serial No.: Docket No.: Licensee Mo. : 88-042 50-280 DPR-32 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 1. REPORT NUMBER 88-028-00

' This report has been reviewed by the *Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control. Very truly yours, Ja ),,?.,c[ j_

• David L. Benson 'Station Manager Enclosure cc: Dr. J. Nelson Grace Regional ~nistrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323