ML20086P322
| ML20086P322 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/17/1991 |
| From: | Zeringue O TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-TM NUDOCS 9112260339 | |
| Download: ML20086P322 (5) | |
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IUA Tenneme Va.ey Awony Post On.e Box 2tm DAau Nabama 35M9 December 17, 1991 O.J *tke'Zenngue Vco Presdent. Browns Ferry Operatons U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Weshington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Hos. 50-259 Tennessee Valley Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - SAFETY PARAMETER DISPLAY SYSTEM (SPDS), RESPONSE TO NRC SAFETY EVALUATION REPORT (SER) OPEN ITEMS This letter provides TVA's response to open items identified by the staff in the SER (Reference 1) regarding BFN's implementation of NUREG-0737, Supplement 1, Item I.D.2, SPDS. Additionally, TVA's SPDS implementation schedule for each BFN unit is summarized.
The reftcenced SER identified open items relating to system and hardware reliability, and human factors engineering design for the BFN Unit 2 Phase I SPDS. These open items were reiterated in Inspection Report (IR) 50-260/90-40-(Reference ?) which required resolution prior to Unit 2
. restart.- TVA completed the necessary actions and the open items were subsequently closed in IR'50-260/91-1:2 (Reference 3).
With regard to the SPDS, the staff P etified open i " ms which required resolution after Unit 2 restart.
"he enclosure to.his letter provides a summary of the Unit 2 open itet; far the SPDS and TVA actions. TVA consid.a that the information requested by NRC has been provided and requests the issuance of a revised SER.
- mme L
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' U.S. Nuclear Regulatory Commission j
December 17, 1991 As previously committed in References 4, 5, and 6, the Unit 2 SPDS will be functional prior to restarting from the next (cycle 6) refueling outage. Following testing the SPDS will become operational during cycle 7 operation. As stated in References 5 and 7, Units 1 and 3 SPDS will be installed prior to the restart of each unit.
Following testing the SPDS will become operational during the first operating cycle after restart for each unit. Additionally, TVA committed in Reference 5 to provide a supplemental response to Generic Letter (GL) 89-06, Task Action Plan Item I.D.2 - Safety Parameter Display System (Reference 8),
addressing certification of compliance with the requirements of NUREG-0737, Supplement 1, within two months af ter the SPDS hun become operational for each unit.
I There are no new commitments contained in this letter.
If you have any questions, contact Raul R. Baron, Site Licensing Manager at (205: 729-7566.
Sincerely,
?
[l'bbNf[lk 0l.
. Zeringue Enclosure cc (Enclosure):
NRC Resiaent Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Atheno, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 l
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c REFERENCES
- 1) NRC letter, dated March 6, 1991, Interim and Final Design of the Safety Parameter Display System at the Browns Ferry Nuclear Plant (TAC Nos. 51223, 51224, 51225, 74601, 74606, and 74611)
- 2) NRC letter, dated February 20, 1991, Notice of Violation, (NRC 50-259/90- 40, 50-260/' 0-40, and 50-296/90-40)
Inspection Report Nos.
1
- 3) NRC letter, dated May 10, 1991, Notice of Violation, (NRC Inspection Report Hos. 50-259/91-10, 50-260/91-10, and 50-296/91-10)
- 4) TVA letter, dated Septemoer 19, ISb9, Browns Ferry Nuclear Plant (BFN) - Response to Request for Additional Information - Safety Parame*.er Display System (STDS)
- 5) TVA letter, dated July 11, 1989, Response to Generic Lettcr (GL) 89 Safety Parameter Display System (SPDS) for Browns Ferry Nuclear Plant and Watts Bar Nuclear Plant
- Phase I Safety Parameter Display System (ISPDS)
Regulatory Framework for the Restart of Units 1 and 3
- 8) NRC letter, dated April 12, 1989, Lisk Action Plan Item I,D,2 -
Safety Parameter Display System - 10 CFR 5 50.54(f) - (Generic Letter No. 89-06)
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ENCLOSURE LROWNS FERRY NUCLEAR PLAlif (BFN)
SAFE!r PARAMETER DISPLAY SYSTEM (SPDS)
SAF2TY EVALUATION REPORT (SER) OPEN ITEMS 1.
NRC 0 PEN ITEM - CONTAINMENT ISOLATION STATUS:
"The audit team concluded that the current containment isolation display will satisfy the requirement of Supplement 1 to NUREG-0737 for ISPDS.
However, TVA should ensure that this requirement continues to be satisfied in its decision regarding whether to provide containment isolation status as part of the final SPDS or on a separate display within visual access of the SPDS operator." (Reference 1, page 3)
TVA PESPONSE:
The BFN SPDS will display primary containment isolation status (PCIS) data. A separate PCIS monitoring system is being developed, which will previde valve position and PCIS group status data to the SPDS computer.
Displays will be provided on SPDS showing a summary of PCIS group status with lower-level displays showing actual valve positions for monitored valves. Additionally, the separate PCIS monitoring system will drive status lights on a control room benchboard panel.
2.
NRC OPEN ISSUE - SPDS CRITICAL SAFETY FUNCTIOES:
"The audit tsam found that the requirement regarding minimum informstion about the five safety functions identified in Supplement 1 to NUREG-0737 was satisfactory for the interim SPDS, however, this requirement would not be fully satisfied for a fully operational SPDS until the licensee fulfills its commitment to provide additional critical safety function parameters. Tr.e licensee has connitted to add the following parameters:
source range monitors, offgas (pre-treatment and post-treatment) effluent monitors, containment radiation monitors, and containment isolation valve status." -(Reference 1, page 6)
TVA RESPONSE:
As requested by the NRC staff, TVA confirms that the BFN SPDS will contain the critical safety function parameters listed in NUREG-1342, Table 3 for BWRs which include the following:
a.
Average Power Range Monitors b.
Source Power Range Monitors c.
RPV Water Level d.
Drywell Temperature e.
RPV Pressure f.
Stack radioactivity Release Rate g.
Offgas Post-Treatment Effluent Monitor h.
Drywell Radiation Levels
- i. Suppression Pool Radiation Levels
. +,, TVA RESP 0f]SE (Centinued)
- j. Dryvell Pressure k.
Dryvell Temperature 1.
Suppression Pool Temperature r.
Suppression Pool Level n.
Containment Isolation Status o.
Drywell Hydrogen Concentration p.
Drywell Oxygen Concentration Note that the SER refers to offgas pre-treatmen effluent monitors. This parameter ir not required by NUREG-1342 and 1s, therefore, not included in the SPDS overview display.
ovever, this information will be available on the Integrated Computer Sys em which implements the SPDS function.
3.
NRC OPEN IFSUE - DISPLAY OF DRYWELL OXYGEN CONCENTRATION "The licensee is evaluating the addition of containment isolation valve status (i.e., as a part of the SPDS or on a separate control room panel) and drywell oxygen concentration. The resultu of the evaluation should be submitted to the NRC-for review and approval, including justification for the location of containment isolation valve status if not integral to the SPDS, and justification for not providing the drywell oxygen concentration." (Reference 1, page 6)
TVA RESPONSE:
Dryvell oxygen concentration has been added to the BFN SEDS parameters.
Primary containment isolation status is integral to the SPPS as described in Item 1 above.
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