View source for AECM-84-0209, Final Deficiency Rept for Unit 1 & Interim Rept for Unit 2 Re Calculated Max Temp for Main Feedwater Movement Guides Exceeding Original Design Limitation for Concrete within Auxiliary Bldg G-line Wall.Also Reportable Per 10CFR21

{{Adams
| number = ML20087P975
| issue date = 04/02/1984
| title = Final Deficiency Rept for Unit 1 & Interim Rept for Unit 2 Re Calculated Max Temp for Main Feedwater Movement Guides Exceeding Original Design Limitation for Concrete within Auxiliary Bldg G-line Wall.Also Reportable Per 10CFR21
| author name = Mcgaughy J
| author affiliation = MISSISSIPPI POWER &amp; LIGHT CO.
| addressee name = Oreilly R
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION II)
| docket = 05000416, 05000417
| license number = 
| contact person = 
| case reference number = REF-PT21-84
| document report number = AECM-84-0209, AECM-84-209, NUDOCS 8404100166
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 5
}}

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{{#Wiki_filter:., 'g MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi M                P. O. B O X 16 4 0. J A C K S O N , MISSISSIPPI 39205 34 APR 6,    all : 01 J AMES P. McGAUGHY, JR.
April 2, 1984 vfCE PatssOE8ef U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30303 Attention:         Mr. J. P. O'Rei'ily, Regional Administrator

==Dear Mr. O'Reilly:==

==SUBJECT:==
Grand Gulf Nuclear Station Units 1 and 2 Docket No. 50-416/417
                                  ,                                    License No. NPF-13 File 0260/15525/15526/16694.4 PRD-84/05, Final Report for Unit 1, Interim Report No. 1 for Unit 2, Main Feed Water Line Moment Guide Temperature AECM-84/0209 On March 29, 1984, Mississippi Power & Light Company notified Mr. R.
Carroll, of your office, of a Reportable Deficiency at the Grand Gulf Nuclear Station (GGNS). The deficiency concerns the calculated maximum temperature for the main feedwater moment guides exceeding the original design basis limitation for the concrete within the auxiliary building G-line wall.
MP&L has determined that this deficiency is reportable under the provisions of 10CFR21 for Unit 1. Re. portability for Unit 2 has not been determined at this time. All current details are contained in our attached Report. We expect to determine reportability and to submit a Final Report for Unit 2 by June 29, 1984.
Yours truly, J. P. McGaughy, Jr.
KDS:dr ATTACHMENT cc:     See page 2 8404100166 840402 PDR ADOCK 05000                                        N.?M(:i AL C'OPY G E7 Member Middle South Utilities System p$
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                       . Mr. J. P. O'Reilly                                           AECM-84/0209 NRC                                                           Page.2
                       - cc:  Mr. J. B. Richard Mr. R. B. McGehee Mr. T. B. Conner Mr. Richard C. DeYoung, Director-                   ,
Office of Inspection & Enforcement U. S. Nuclear Regulatory Connaission Washington, D.C. 20555 Mr. G.        B.' Taylor South Miss. Electric Power Association P. O. Box 1589 Hattiesburg, MS 39401 e
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Attschmsnt to AECM-84/0209 Psga 1 of 3 FINAL REPORT FOR UNIT 1
             ,                                   INTERIM REPORT No. 1 FOR UNIT 2
: 1. Name and address of 'the individual ... informing the commission:
J . . P . Mc Ga ughy , Jr .
Vice-President, Nuclear P.O.. Box 1640                                                         .
Jackson, Mississippi 39205 2.-   Identification of the facility _ . . . - which . . . contains a deficiency:
Grand Gulf Nuclear Station (GGNS) Unit 1 Port Gibson, Mississippi 39150 Determination of reportability for Unit 2 is continuing at this t ime .
: 3. Identification of the . firm . . . supplying the basic component which . . .
contains a' deficiency:
LSupplied to Grand Gulf .by the Bechtel Power Corporation, Gaithersburg, Maryland.
: 4. Nature of the deficiency .. . and the safety hazard which .. . could be created by 'such a deficiency . . . :
A. Description of the Deficiency During low power operation of Grand Gulf Unit 1, the main . steam line moment. guides, located within'the auxiliary building'G-line
. ,                              wall, experienced an overheating problem. In reviewing the i                                applicable calculations it was discovered that heat losses from
: f.                               the uninsulated portions. of the moment guides to the concrete ~ wall l
had been neglected in the original analysis for the main steam and
;                                main feedwater lines.
                                . A heat transfer reanalysis of the moment guide'' swas perform'ed using a more. detailed model based on as-built conditions. This analysis.has shown that the temperature of the' concrete wall near the' main feedwater line moment guides would exceed 300*F. If the-L L                              ' concreteL temperature exceeds 300*F- (the ' design lLniting tempera-
!                               . ture' of the G-line wall) the potential exists for degradation of -
L                               . concrete properties .and strength.
However,: for_ the main steam line moment guides, the reanalysis indicated' that the concrete temperature ILuits would not be exceeded.
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i Attschesnt to AECM-84/0209 Page 2 of 3 B.      Analysis of Safety Implications Degradation of the auxiliary building G-line wall, which encloses
                           'the main steam and main feedwater line moment guides, from temperatures 'in excess of the 300*F limiting temperature could
                            . result ~in failure of the wall to perform its intended safety function for the following reasons:
: 1. The wall forms a part of the secondary . containment which in conjunction with the standby gas treatment system serves to limit doses within the guidelines of 10CFR100 and 10CFR50, during the design basis accident.
: 2. The wall contains the main steam and feedwater line moment guides which are necessary to protect the outboard Main Steam Isolation Valves (MSIV's) from excessive loads due to a postulated pipe failure in the turbine building. The basis for these restraints is the NRC's Branch Technical Position MEB 3-1, paragraph B.I .b(1)(c) .
: 15.  ?The date on which the information f such deficiency ... was obtained.
                                                     ~
: Mississippi. Power and' Light received Iinformation of the deficiency on January- 11, 1984. An' evaluation was performed and the deficiency was reported to Mr. R. Carroll, of fyour office, as a reportable deficiency for Unit 1 on March 29, 198 . - ) The MP&L' " Responsible Of ficer," Mr.- J. P.
McGaughy, Jr. , ivi11~ be notified when he' returns to - his of fice.
In' the case .of the basic component ... the number and location of all 6.
such components.
There are two. feedwater ' penetrations in the auxiliary building G-line
                                                                      ~
wall at'GGNS Unit ~1.
              .7.- ~ The corrective 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.
A._   - Corrective Actions Taken A Design Change ' Package (DCP) 83/4106 has been issued and implemented to insure a steel-concrete interface temperature below 200*F for both the main steam and main feedwater line moment
                           ' guides. The. corrective . actions taken .were as follows:
                           -1. Insulation was 'added to main feedwater line moment guides.
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2;  .The Moment guide cooling' system was modified for additional cooling capacity.
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       .g' e Artschasat to AECM-84/0209 Pegs 3 of 3
: 3. Temperature monitors were installed on the main feedwater line G-line wall moment guides.
B.        Responsible Individual Unit l' J. E. Cross Plant Manager Mississippi Power & Light Co.
C.        Length of Time to Complete Actions All corrective actions per DCP 83/4106 with the exception of the moment guide cooling system balance testing have been completed on Unit 1. The balance tests are for chill water and air flow balance and are scheduled for completion during power ascension under rated conditions.
 ,                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 o f fe r.
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