AECM-84-0159, Final Deficiency Rept Re anti-rotational Setscrews in Anchor Darling Glove Valves.Initially Reported on 840213.Setscrew Tightened & Stem Collar Threads Staked Using Ctr Punch. Also Reported Per Part 21 for Unit 1

Final Deficiency Rept Re anti-rotational Setscrews in Anchor Darling Glove Valves.Initially Reported on 840213.Setscrew Tightened & Stem Collar Threads Staked Using Ctr Punch. Also Reported Per Part 21 for Unit 1

ML20087H806
Person / Time
Site:	Grand Gulf
Issue date:	03/14/1984
From:	Mcgaughy J MISSISSIPPI POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-84 AECM-84-0159, AECM-84-159, NUDOCS 8403210192
Download: ML20087H806 (5)

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E MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B O X 1640, J A C K S O N. MIS SIS SIP PI 3 9 20 5 19 A 9 '. l 0 March 14, 1984 J AMES P. McGAUGHY. JR vics reassoamt U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30303 Attention: Mr. J. P. O'Reilly, Regional Administrator

SUBJECT:

Grand Gulf Nuclear Station Units 1 and 2 Docket No. 50-416/417 Licens e No. NPF-13 File 0260/15525/15526/16694.4 PRD-84/02, Final Report ,

Ant i-Rotational Set screws in Anchor Darling Glove Valves AECM-84/0159 On February 13, 1984, Mississippi Power & Light Company notified Mr. R.

Carroll, of your office, of a Reportable Deficiency at the Grand Gulf Nuclear Station (CCNS) Unit 2 Construction Site. The deficiency concerns the looseniag of the anti-rotational setscrew in Anchor Darling glove valves.

MP&L has evaluated this deficiency and has determined that it is report-able under the provisions of 10CFR21 for Unit 1 and 10CFR50.55(e) for Unit 2.

Details are included in our attached Final Report.

Yours truly,

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J. P. McGaughy, Jr.

fD7 KD3:dr ATTACHMENT cc: See page 2 8403210192 840314 PDR ADOCK 05000416 S PDR OFFICI AL COPY Member Middle South Utilities System

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l Mr. J. P. O'Reilly AECM-84/0159 NRC Page 2 cc: Mr. J5 B. Richard Mr. R. B. McGehec Mr. T. B. Conner

. Mr. ' Richard . C. DeYoung, Director

' 0f fice 'of Inspection & Enforceo6nt .

'<: ' U. S. Nuclear Regulatory ' Commission

. Washington, D.C. 20555-Mr. C. B.'

Taylor South Miss. Electric' Power Association P. O. Box 1589 . ., ,

Hattiesburg,' MS 39401 v

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, FINAL REPORT PCR PRD-84/02 .

1. .Name and address of the indihidual ... informing the' commission:

'J. P. McGaughy, Jr. . ,

Vice-Pres ident. . Nuclear P.O. Box 1640

' Jackson, ' Mississippi 39205 - ,

2.- Identification of the' facility . .. which ' . . . contains a deficiency:

L Grand' Gulf ' Nuclear Station (GCNS) Unit s 1 and 2 Port Gibson, Mississippi 39150 f This deficiency is reportable under.10CFR50.55(e) for Unit 2. It is not reportable under-10CFR21 for Unit 2 since the affected equipment has not

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been received by MP&L.

3. Identification of the firm ... supplying the basic component which ...

.contains a deficiency:

General Electric Company .

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Nuclear Energy BusinesJ Operation San ~ Jose, California

4. Nature of the deficiency . . . and the ' safety ' hazard which .. . could be created by 'such a deficiency. .. .:

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A. Description of the Deficiency The three affected valves identified are as follows:

HPCS test return to Condensate Storate Tank (CST); Valves E22-F010,-F011 -

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HPCS test return to Suppression. Pool; Valve E22-F023 The valves in both Unit 1'and Unit 2 are af fected.

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4 The valve sten rotation is prevented by a key held in place by a

, , stem collar. ~ Thel setscrew holding the anti-rotational stem collar in position could loosen because of normal system vibration, causing the sten collar.to slide and the key to fall from its keyway.L EWithout the key in place, the stem may. rotate with the motor operator without ' vertical movement. This rotation renders

' the valve inopersble.' .

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"? ' Attcchesnt to ' AECM-84/0159 -

. Pega 2 of 3 B. - Analysis ^ of- Safety Implications

> ' ' These valves are opened 'during testing of the High Pressure Core Spray (HPCS) System to bypass the reactor. _ They are normally closed during plant operation. Because of _ the subject deficiency,

.these valves could remain open after the completion.of a test, without the awareness"of. the Control Room operators.

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If both F010 and Poll, or P023 alone are 'open'during an accident, HPCS flow would be diverted to the Condensate Storage Tank (CST) .

or Suppression ' Pool, thus bypassing the reactor. Also, the water fras.the Suppression Pool could be diverted to the CST which is located outside the containment and -vented to the atmosphere.

< This condition may result in exceedingEradiation dose limits specified in '10CFR100, p.

l5. Ese 'date on _which the information of such deficiency ... was obtained.

Mississippi Power and Light- first received information of the generic

' deficiency in IE Information Notice 83-70 on October. 31, 1983. This

' notice ' ves being investigated - for _ applicability to GGNS. On December

,15,:1983, MP&L received notice.from General Electric that the deficiency appliedito GGNS. We reported the deficiency to Mr. R. Carroll, of your office, as being reportable under the provisions of 10CFR50.55(e) for

-Unit 2. ; We reported the deficiency to Mr. D. Verre11i as being report-able under 10CFR21 for Unit 1 on February 22, 1984. On that date Mr.

-Verre1111 agreed that the date for the submittal of the 10CFR50.55(e) report would be ~ acceptable for the subnittal of the 10CFR21 report. The

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MP&L " Responsible Officer," .Mr. 'J. P. McGaughy, Jr. , will be notified when he returns to his office.

16 . . ;fn the case of -th'e basic component '... the _ number and location of all

. such c omponent s .

Locations of other components were 'given by General Electric in their

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- letter .of Dec ember- 14, 1983, to the NRC, -Washington, D. C.

7.. :The currective action which has been taken . .. the name of the individual ... responsible ~ for the action; and the length of time that

,has been ... taken to complete the action.

Corrective Actions Taken

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On Unit 1 the setscrew was tightened and the stem collar threads

,"" ,;'. 'were staked using a center; punch. Corrective actions for Unit 2 Cgh will be either the same sas for. Unit 'l or a nuclear. grade thread

' ' locking c'ompound will be applied to the set screw threads.

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. AttcchmInt to AECM-84/0159

' Pcg2 3 cf 3 B. Responsible Individual Unit 1 Unit 2 J. E. Cross T. H. Cloninger Plant Manager Unit- 2 Project Manager Mississippi Power & Light Co.- Mississippi Power & Light Co.

C. lLenath of Time to Complete Actions

The corrective actions on Unit I were completed by November 21, 1983. Corrective actions on Unit 2 will be' completed prior to turnover to MP&L.

8. Any advice related to the deficiency ... that has been, is being, or

;. will be given to purchasers or licensees

As the deficiency did not originate with MP&L, we have no advice to offer.

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