ML18152A633

LER 87-036-00:on 871202,during Hot Shutdown Inner Door of Containment Personnel Air Lock Exceeded Leakage Criteria for Periodic Test 16.7.Caused by Inadequate Seal.Shim Welded to Actuator Mechanism to Allow Proper sealing.W/871231 Ltr

ML18152A633
Person / Time
Site:	Surry
Issue date:	12/31/1987
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
87-042, 87-42, LER-87-036, LER-87-36, NUDOCS 8801120430
Download: ML18152A633 (4)

Text

NRC Form 366 ,19-831 e e POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 LICENSEE EVENT REPORT (LER)

FACILITY NAME (11 DOCKET NUMBER (21 I PAGE 131 C:::111"1"V Pnwc.r C:::+ .. +:~- 1 lni+ 1 o I 5 I o Io I o I 71 RI n I 1 IOF n I<

TITLE (41 Containment Air Lock Leakac e Due To Inadequate Seal '

EVENT DATE (51 LER NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YEAR tit SE~~~~~~AL ti ~E~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 1 2I oI 2 s. 7 sI 7 - oI 3 IG - ol o 1 I 2 3 I 1 sI 7 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: /Check one or more of the follo<ying/ (111 OPERATING MODE (Bl N 20.402(b) 20.405(c) 60.73(ol(2J(ivl 73.71(b)

..x..

20.406(1J(1)(i) 60.36(cll1l

- 50.73(11(2)(v) 73.71 lcl 20.406(1)(1 l(ji) 20.406(ol(1 )(iii) -

60.361cll2l 60.73(1)121(i) -- 50.73la)(2J(vii) 60.73(1)(2)(viiil(A) - OTHER (Specify in Abstrect bstow and in Text, NRC Form 366A}

20.406(11(1)(1v) 20.406(ol(1 l(vl - 60,73(11(2Jlii) 60.73(11(2)(iiil -

LICENSEE CONTACT FOR THIS LER (12) 50.73(11(2HvllillBI 60.73(11(2Jlxl NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 8 I OI 4 31 5 I 71 -1 3 I 1 I 81 4 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)

MANUFAC- MANUFAC-CAUSE SYSTEM COMPONENT TURER TURER X 81DAIUI I W131012 y I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPFCTED (141 MONTH OAY YEAR EXPECTED.

SUBMISSION h YES /If yes, complete EXPECTED SUBMISSION DA TEI DATE (151 I I I ABSTRACT (Limit to 1400 spaces, i.e., approximately fifteen single-space typewritten lines) (16)

On December 2, 1987 at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />, -with Unit 1 at hot shutdown, the inner door of the containment personnel air lock {EIIS-AL}

exceeded the leakage acceptance criteria for Periodic Test 16.7, "Personnel Air Lock Leakage Test". Containment integrity, as defined in Technical Specification 1.0.H.4, was briefly violated when operations personnel opened the outer air lock door in order to exit the containment following the completion of the test. At 0655 hours0.00758 days <br />0.182 hours <br />0.00108 weeks <br />2.492275e-4 months <br />, a satisfactory leakage test was performed on the outer air lock door. Containment integrity was again briefly violated when mechanics opened the outer door to gain access to the personnel air lock* in order to make repairs to the inner door. At 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br />, upon completion of the repairs, a satisfactory leakage test was performed on both the inner and outer air lock doors. This event was due to the failure of the inner door of the personnel air lock to seal tightly. The leakage was attributed to spacing in the actuator mechanism which did not ailow for proper seating of the actuator piston. A 1/2 inch shim was welded to the actuator mechanism to correct the spacing between the piston and the seating surface to ensure proper sealing of the door.

8801120430 871231.

PDR ADDCK 05000280 S PDR NRC Form 388

e e POW 28-06-01 NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (9-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 FACILITY NAME (11 DOCKET NUMBER 121 LER NUMBER 161 PAGE (3!

Surry Power Station, Unit 1 o I5 Io I o I o I 2 I s Io R 17 - o I ~, Ii - o I o nl  ? OF nI~

TEXT /If mo,w - ii ,eqund, u* !KldltioMI NRC Fomi 366A '*I 1171 1.0 Description of the Event on December 2, 1987 at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />, with Unit 1 at hot shutdown, the inner door of the containment personnel air lock {EIIS-AL} exceeded the leakage acceptance criteria for Periodic Test 16.7, "Personnel Air Lock Leakage Test". Containment integrity, as defined in Technical Specification 1.0.H.4, was briefly violated when operations personnel opened the outer air lock door in order to exit the containment following the completion of the test. At 0655 hours0.00758 days <br />0.182 hours <br />0.00108 weeks <br />2.492275e-4 months <br />, a satisfactory leakage test was performed on the outer air lock door. Containment integrity was again briefly violated when mechanics opened the outer door to gain access to the personnel air lock in order to make repairs to the *inner door. At 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br />, upon completion of the repairs, a satisfactory leakage test was performed on both the inner and outer air lock doors.

2.0 Safety Consequences and Implications The personnel air lock is the cont~inment's normal entry and exit point for personnel and tools. It consists of a horizontal cylinder with gasketed doors at each end. A requirement for containment integrity is that at least one door must be properly closed and sealed. Technical Specifications require that the unit be brought to hot shutdown within six hours and to cold shutdown within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, unless corrective measures have been completed. At the time of these events, the unit was in hot shutdown, and repairs to the inner air lock door were completed within six hours. Therefore, the health and safety of the public were not affected.

3.0 Cause This event was due ' to the failure of the inner door of the personnel air lock to seal tightly. The leakage was attributed to spacing in the actuator mechanism which did not allow for proper seating of the actuator piston.

NAC FOAM 366A

• U.S.GPO: 1986-0,624-538/455 (9-831

e e POW 28-06-01 NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION 19-83)

LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME 111 DOCKET NUMBER 121 LEA NUMBER 161 PAGE 13)

Surry Power Station, Unit 1 0 1s Io Io Io I 2 I i:i I n RI 7 - o 13 16 - o I o oI 3 OF o 13 TEXT /If,,,,,,.~ ia , . , - , u* MlditionM NRC Fom, 315&4'*1117) 4.0 Immediate Corrective Action(s)

A 1/2 inch shim was welded to the actuator mechanism to correct the spacing between the piston and the seating surface to ensure proper sealing of the door.

5.0 Additional Corrective Action(s)

A Technical Specification change will be submitted to allow entry to and exit from the containment personnel air lock to repair the inner air lock door if it is inoperable.

6.0 Action(s) Taken to Prevent Recurrence None required.

7.0 Similar Events None.

8.0 Manufacturer/Model Number W. J. Wooley Company/Not applicable.

NRC FORM 366A 19-831

• U.S.GPO: 1986-0-624*536/455

e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 316 Surry, Virginia 23883 December 31, 1987 U.S. Nuclear Regulatory Commission Serial No.: 87-042 Document Control Desk Docket No.-: 50-280 016 Phillips Building Licensee No.: DPR-32 Washington, D.C. 20555 Gentlemen:

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 87-036-00

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