ML20214C926: Difference between revisions

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#REDIRECT [[AECM-86-003, Forwards Response to Items Addressed in Section 4 of NRC Interim SER & Request for Addl Info Re Reg Guide 1.97 Commitments.Design,Specs & Schedule for Performing Work Being Developed]]
| number = ML20214C926
| issue date = 02/14/1986
| title = Forwards Response to Items Addressed in Section 4 of NRC Interim SER & Request for Addl Info Re Reg Guide 1.97 Commitments.Design,Specs & Schedule for Performing Work Being Developed
| author name = Dale L
| author affiliation = MISSISSIPPI POWER & LIGHT CO.
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000416, 05000417
| license number =
| contact person =
| case reference number = RTR-REGGD-01.097, RTR-REGGD-1.097
| document report number = AECM-86-0030, AECM-86-30, TAC-51094, NUDOCS 8602210332
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 4
| project = TAC:51094
| stage = Request
}}
 
=Text=
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MISSISSIPPI POWER & LIGHT COMPANY M
                        ]                           Helping Build Mississippi P. O. B OX 164 0. J AC K S O N MIS SISSIP PI 39215-1640 February 14, 1986 NUCLE AR LICEN$1NG & SAFETY DEPARTVENT U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C.            20555 Attention:        Mr. Harold R. Denton, Director
 
==Dear Mr. Denton:==
 
==SUBJECT:==
Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 License No. NPF-29 Response to NRC Request For Additional Information (RAI) on MP&L's Position Report on Regulatory Guide 1.97 (Rev. 2)
 
==References:==
: 1) MAEC-85/0409
: 2) AECM-85/0059 AECM-86/0030 This letter is being provided to respond to the staff's Interim Safety Evaluation Report and Request for Additional Information (RAI) (Reference 1) regarding Mississippi Pcwer & Light's (MP&L's) Position Report on Regulatory Guide 1.97 for Grand Gulf Nuclear Station (GGNS) (Reference 2).
AttachmenkA*providesMP&L'sresponsetoeachoftheitemsaddressedin Section 4 of the Staff's Interim Safety' Evaluation. The additional R.G.            1.97 commitments addressed in Attachment A were not previously anticipated and were not included in the planning for the first GGNS refueling outage (RF01).
MP&L is currently developing the design, specifications, and schedule for performing this work and will notify your office if the implementation schedule cannot be met in accordance with Operating License Condition 2.C.(36).
Please advise us by March 14, 1986 if this is acceptable and if you require any additional information.
Yours truly, L. F. Dale Director DLL/GWS/SHH:dmm Attachment cc:      (See Next Page)                                                  9 06 fP Member Middle South utilities System J14AECM86012701 - 1 i                                                                                                    ._.
 
AECM-86/0030 Page 2 cc:  Mr. O. D. Kingsley, Jr. (w/a)
Mr. T. H. Cloninger (w/a)
Mr. R. B. McGehee (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 Dr. J. Nelson Grace Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 J14AECM86012701 - 2
 
Attachment A AECM-86/0030 IT&L Responses to NRC Requests for Additional Information (RAI)
RAI #1:
Primary containment isolation valve position--the licensee should provide seismic qualification for the indicating lamps; the licensee should verify that the indication of the valves not located on the isolation valve status panel is located in the control room.
MP&L Response:
MP&L will provide seismic qualification for indicating lamps for those primary containment isolation valves with position indication presently located on seismit. ally qualified panels (e.g. control room panels IH13-P870 and 1H13-P601). As a matter of clarification, seismic lamps will not be installed in the isolation valve status panel (IVSP, panel IH13-P858) since this panel is seismically supported only and is not seismically qualified. The IVSP provides valve status indication only as a control room " human factors" enhancement. The primary containment isolation valve status lights on this panel are also indicated on the above referenced control room panels which are seismically qualified and will be provided with seismic lamps. In addition, MP&L confirms that the primary containment isolation valves with remote status indication and not presently located on the IVSP have status indication in the Control Room.
RAI #2:
Core spray system flow--environmental qualification should be addressed in accordance with 10 CFR 50.49.
MP&L Response:
The GGNS LPCS flow transmitter (E21-N003) is located in room lAll4 which has been analyzed and found to be in a mild environment.
Therefore, this item is not required to be environmentally qualified per 10 CFR 50.49.
RAI #3:
Standby liquid control system storage tank level--environmental qualification should be addressed in accordance with 10 CFR 50.49, 4
MP&L Response:
The following discussion clarifies MP&L's previous position that the installed Category 3 (non-Class t-E) instrumentation is considered acceptable for R.G. 1.97 implementation and is, therefore, not required for 10 CFR 50.49 consideration.    [Please refer to the Environmental Qualification column and Position 17 for SLCS Storage Tank Level, provided in the GGNS R.G. 1.97 Position Report dated February 28, 1985 (AECM-85/0059).]
J14AECM86012701 - 4
 
Attachment A AECM-86/0030 MP&L Responses to NRC Requests for Additional Information (RAI)
SLCS is designed as an alternate means to the control rods for reducing reactivity in order to achieve safe shutdown. An Anticipated Transient Without Scram (ATWS) event could require the initiation of SLCS to mitigate the adverse condition. However, an ATWS is not assumed to be associated or coupled with a LOCA or High Energy Line Break (HELB) design basis event and, therefore, SLCS is not required to function to mitigate the effects of a LOCA or HELB.
An ATWS event does not constitute a harsh environment for 10CFR50.49 environmental qualification. Based on this, the SLCS instrumentation would not require environmental qualification per 10 CFR 50.49.
Therefore, it is considered that the existing Category 3, non-Class IE (non-environmentally qualified) instrumentation will perforn the intended safety function and meets the intent of R.G. 1.97.
RAI #4:
Cooling water flow to engineered safeguards feature system components--environmental qualification should be addressed in accordance with 10 CFR 50.49.
MP&L Response:
MP&L interpreted this variable ta be main system flow.
The present GGNS instrumentation that monitors total cooling water flow to engineered safeguards feature (ESF) system components is located in the SSW Basin area which has been determined to be a mild environment.
Thus, these instruments are not required to be qualified per 10 CFR 50.49.
RAI #5:
Status of standby power and other energy sources important to safety--the licensee should provide control room indication for the parameter starting air pressure for the high pressure core spray diesel generator.
MP&L Response:
MP&L will provide an input to the common trouble alarm in the control room for the low HPCS diesel generator starting air pressure. Category 2 requirements will be met for this equipment. However, environmental qualification to 10 CFR 50.49 vill not be necessary since the diesel generator room and the control room are both in mild environmental areas.
J14AECM86012701 - 5}}

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