View source for AECM-86-0376, Final Deficiency & Part 21 Rept 4 Re Low Flow Condition Through Standby Svc Water (SSW) Pump A.Initially Reported on 820415.Procedures to Ensure That Min Pump Flow Provided When SSW Sys Automatically Started,Issued

{{Adams
| number = ML20214T931
| issue date = 11/25/1986
| title = Final Deficiency & Part 21 Rept 4 Re Low Flow Condition Through Standby Svc Water (SSW) Pump A.Initially Reported on 820415.Procedures to Ensure That Min Pump Flow Provided When SSW Sys Automatically Started,Issued
| author name = Kingsley O
| author affiliation = MISSISSIPPI POWER &amp; LIGHT CO.
| addressee name = Grace J
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION II)
| docket = 05000416, 05000417
| license number = 
| contact person = 
| case reference number = REF-PT21-86-286-000, REF-PT21-86-386-000
| document report number = AECM-86-0376, AECM-86-376, PT21-86-386, PT21-86-386-000, NUDOCS 8612090061
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 5
}}

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MISSISSIPPI POWER & LIGHT COMPANY
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tstilMIME Helpinhuild Mississippi P. O. B O X 16 4 0.pJb C K S O N, M I S SI S S I P PI 39215-1640 t,Nhvember 25, 1986 O. D. KINGSLE Y, J R.
VICE PRESIDENT NUCLE AR OPERATIONS U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W. Suite 2900 Atlanta, Georgia 30323 Attention:           Dr. J. Nelson Grace, Regional Administrator

==Dear Dr. Grace:==

==SUBJECT:==
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/0511/0512 PRD-82/21, Final Report No. 4, SSW "A" Loop System Flow AECM-86/0376

==Reference:==
: 1) AECM-82/214, 5/17/82
: 2) AECM-82/278, 6/14/82
: 3) AECM-82/408, 9/20/82
: 4) AECM-84/341, 7/31/84 On April 15, 1982, Mississippi Power & Light Company notified Mr. F.
Cantrell, of your office, of a Potentially Reportable Deficiency (PRD) at the Grand Gulf Nuclear Station (GGNS) construction site. The deficiency concerns a low flow condition through the "A" Standby Service.. Water (SSW) Pump when started in response to an automatic initiation of-the Reactor Core Isolation Cooling (RCIC) system.
We have determined that this deficiency is reportable under the provisions of both 10CFR50.55(e) and 10CFR21 for Unit 1 and 10CFR50.55(e) for Unit 2.
Attached is our Final Report No. 4.
This deficiency is applicable to both Unit 1 and Unit 2.                  To prevent recurrence on Unit 2, minimum flow requirements will be taken into consideration when Unit 2 subsystems are designed.
8612090061 861125 PDR 6         ADOCK 05000416 PDR ODK:Im Attachment cc:      (See Next Page)
J10AECM86112501 - 1                Member Middle South Utilities System

           -                                      AECM-86/0376 Page 2
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cc: Mr. T. H. Cloninger (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. R. C. Butcher (w/a)
Mr. James M. Taylor, Director (w/a)
Office of Inspection & Enforcement U. S.-Nuclear' Regulatory Commission Washington, D. C. 20555 l
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Attachment A to AECM-86/0376 FINAL REPORT NO. 4 FOR PRD 82/21
: 1.      Name and address of the individual ... informing the comission:
: 0. D. Kingsley, Jr.
Vice-President, Nuclear Operations P.O. Box 1640
                      -Jackson, Mississippi 39205 Notification of Part 21 applicability made to Mr. F. Cantrell, NRC, Region II by telephone on May 10, 1982.
4          2.      Identification of the facility ... which ... contains a deficiency:
Grand Gulf Nuclear Station (GGNS) Units 1 and 2 i                     Port Gibson, Mississippi 39150 10CFR21 is applicable only to Unit 1
: 3.      Identification of the firm ... supplying the basic component which ...
contains a deficiency:
The design was provided 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                                                              ..
The "A"  loop of the Standby Service Water (SSW) System is designed to automatically provide cooling water to the Reactor Core Isolation Cooling (RCIC) Room Cooler on a RCIC initiation signal. As soon as the steam supply valve to the RCIC system leaves the fully closed position, an initiation signal is provided to start the SSW loop "A" pump, open the pump discharge valve, and the cooling tower return valve. This provides a flow path for the RCIC Room Cooler.
The flow in the SSW system during this mode of operation is significantly less than that required to keep the SSW pump cool during operation. Approximately 95 gpm is used in the system during-this mode of operation. The SSW pump requires approximately 2000                              l gpm to prevent heat buildup in the pump.
The design does not allow for a minimum flow path in the SSW loop "A" when the SSW System is automatically started due to a RCIC initiation signal. All other automatic starts of both the SSW loop "A" and SSW loop "B", initiated by an automatic start of another system, provide adequate flow in the SSW loops to prevent puup                                !
damage.                                                                                       l i
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Attachment A to AECM-86/0376 B. Analysis of Safety Imolications The loss of the SSW loop "A" pump could prevent the removal of heat from plant auxiliaries, such as the Standby Diesel Generator 11 and the Low Pressure Core Spray (LPCS) Room Cooler, which require cooling during an emergency shutdown of the plant. It could also prevent the use of the SSW system as the ultimate heat sink used for removal of the decay heat generated by the reactor core.
: 5.        The date on which the information of such deficiency ... was obtained.
Mississippi Power and Light received information of the deficiency on April 15, 1982. We reported the deficiency to Mr. F. Cantrell, of your office, as a Potentially Reportable Deficiency on that date and as reportable under 10CFR21 by telephone on May 10, 1982. Since that date MP&L has filed three (3) Interim Reports to inform the Commission of the progress and status of the evaluation of this deficiency.
: 6.        In the case of the basic component ... the number and location of all such components.
The deficiency affects only the "A" loop of the Standby Service Water System at GGNS, We do not have knowledge of the location of other deficient designs of this type other than at GGNS.
: 7.        The corrective action which has been taken ... the name of the individual ... responsible for the ac, tion; and the length of time that has been ... taken to complete the action.
A. Corrective Actions Taken Plant procedures which will ensure that minimum pump flow is provided when the SSW system is automatically started due to a RCIC initiation have been issued.
An interim design change was implemented in April, 1983, to establish minimum flow protection utilizing the basin recirculation line, 20"-HBC-171, as a minimum flow path for the SSW pumps. The SSW system control logic was modified to ensure that when the SSW pumps were started on a RCIC auto start, a Residual Heat Removal (RHR) A, B, and C manual start, or a Low Pressure Core Spray (LPCS) start, the basin recirculation valve (P41F006) would open, provided the RHR heat exchanger inlet and outlet valves (P41F014 and F068) were not fully open. Manual butterfly valve P41-F002 in the basin recirculation line was throttled to ensure that the pump would not reach run out conditions and, at the same time, would maintain required flows to .
the system components while operating in this configuration. This method of minimum flow protection was identified as an interim desian change since pump minimum flow requirements would change following installation of the larger pump impellers and motors required for resolution of PRD 81/17, Flow Rate in the SSW System Loops A and B and Loss of SSW Basin Transfer Capability (Ref. 4).
J10AECM86112501 - 5

1
  '                                                  ~
        ,                                           -Attachment A to AECM-86/0376 Subsequent implementation of the permanent design change required by PRD .81/17, however,:only necessitated replacement of the butterfly valve in the basin recirculation line with a globe valve due to the potential for valve damage from the. increased pump total developed head. Accordingly, no further modifications to the SSW system have been required.to resolve PRD 82/21.
Our Architect / Engineer is aware of the problem and will ensure that minimum flow requirements are taken into consideration when Unit 2 subsystems are designed.'
B. Responsible Individual Unit 1                                 Unit 2 J. E. Cross       "
H. D. Morgan Site Director                          Unit 2 Constr. Superintendent Grand. Gulf Nuclear Station            Grand Gulf Nuclear' Station Mississippi Power & Light Co.         Mississippi Power & Light Co.
C. Length of Time to Complete Actions Mississippi Power and Light received information of the deficiency on April 15, 1982.
The required procedures have been issued and permanent design change has been implemented.
: 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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