ML19322E991
| ML19322E991 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/13/1980 |
| From: | Gilberts D NORTHERN STATES POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-01B, IEB-79-1B, NUDOCS 8004040456 | |
| Download: ML19322E991 (4) | |
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3 MSP NORTHERN STATES POWER COMPANY M I N N E A PO L,l s. M I N N E S OTA 55401 March 13,1980 Mr. James G. Keppler Director, Region III Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 799 Roosevelt. Road Glen Ellyn, IL 60137
Dear Mr. Keppler:
PRAIRIE ISLAND NUCLEAR GENERATING PL/ INT Docket Nos. 50-282 and 50-306 In response to IE Bulletin 79-01B, the following is offered:
(Delay of this response till March 14, 1980 was approved by Mr. J. Hughes of your office by telephone on February 29, 1980.)
ITEM NO. 1 Attached Appendix A includes the " Master List" of all Engineered Safety Feature Systems required to function under postulated accident conditions.
ITD1 NO. 2 The Master List includes individual lists by system and attached to each list are the evaluation work sheets for each component.
These sheets provide infor-mation requested to assist in determining whether the canponents are qualified for the conditions under which hey are expected to operate.
ITEM NO. 3 We have provided the reference material, Appendix B, in the forn of letters test reports, etc., which were used to verify that the components have been qual.ified.
It is our understanding that when the FSAR and WCAP's were used as the reference, they need not be attached.
DISCUSSION As a result of our ongoing review of systemi and new requirements resulting from the TMI Lessons Learned, we have already initiated several modifications which include the replacement of instruments, limit switches and solenoid valves.
Some of these modifications will be made during our next September 1980 and January 1981.
two outages, fulfillment of TMI Lessons Learned requirements.These dates correspond with our intended I
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9 Mr. Jrmes G. K:ppler P:gn 2 March 13, 1980 The requirement for locating components above the flood level, other than those addressed in the initial accident analyses, is a new one and we have addressed it herein. The flood level of 705 feet 9 inches is based on a LOCA.
It will be noted that some components are listed in the attached sheets as being located below flood level. Those that are below flood level'and required only for an HELB, will not be modified since they are located well above HELB flood level, and will not be required in the event of a LOCA.
Specified and demonstrated accuracies for components under accident conditions have been requested. This also is a new requirement. On March 3, 1980, a visit was made to Westinghouse to discuss their performing an evaluation of accident effect on setpoint accuracies needed to meet the accident condition.
We are presently awaiting a proposal from Westinghouse. We will keep you appraised of any resultant program, including a schedule for initiation and completion. Aging requirements have been requested. This is presently under discussion by the Owners Group. We await the results of these discussions.
Limit switches used on the letdown isolation orifice control valves which de-note "0 PEN" have been replaced with switches qualified for the LOCA environ-ment, but do not meet the flood requirement.
In reference to Bulletins 78-04 and 79-28 which also addressed limit switches, we note reference to the require-ment for limit switches used for " valve position circuitry" related to contain-ment isolation valves. We believe this requirement is not a licensing issue.
Our policy has been to qualify those switches which are used for interlocking and control. When the requirement for safety system monitoring, as discussed in NUREG-0585 and 0660 and Regulatory Guide 1.97, are made a condition of the license, we will then proceed to replace the limit switches used for valve position indication.
The Barton steam flow transmitters are not presently qualified for a LOCA.
Steam flow signals are not used to provide protection against steam pipe rup-ture. Reference FSAR, Section 14.2.5.
In a LOCA, containment pressure along with other signals are used as the parameters for mitigating the consequences of the accident. For a HELB, Appendix I - FSAR, steam flow signals are used, and the present transmitters will meet the environmental requirements. Trans-mitter replacement is planned; however, it is due to other factors such as trans-mitter problems not associated with the environment. Environmentelly qualified transmitters will be used for this replacement.
Signal converters used to convert the electrical signal to a pneumatic signal for the steam generator power operated relief valves are not environmentally qualified. The PORV's are noted in the emergency procedures to effect an orderly cooldown. The transient analysis assumed initial control of pressure to hot shutdown conditions by CODE safety valves. Pressure control for long term cooldown can be accomplished without the signal converters, if necessary.
These valves are separated physically such that the HELB environment should only affect one signal converter and valve operator. Only one PORV is needed i
for controlling pressure to assure cooldown. We believe the signal converters are adequate as they are and no further qualification is necessary.
i
s Mr. Jam:s G. K:ppler Page 3 March 13, 1980 f
The safety injection flow meters are Barton 386. WCAP 7410 discusses the qualification of Barton 332, Mod 1 transmitter which was the prototype for 386 used for pressurizer level. The WCAP covers the radiation qualification of those components most susceptible to radiation e.g., electronic-boards, strain gage, zero and span pots, etc.
We conclude that the Model 332 is qualified for this use.
Terminal blocks are not qualified for LOCA/RELB conditions. We are contacting the supplier to determine whether he has any information regarding the quali-fying of the blocks.
It is our opinion that the materials of construction are such that the accident environment would have no effect on the blocks, except submergence.
In any event, we have initiated an in-house program to perform qualification testing analysis. We are preparing requests for pro-posals to be sent to several test laboratories to determine whether they can qualify the blocks. We intend to keep you informed of our progress and results of such tests.
Our criteria for determining whether a solenoid valve should be qualified was as follows:
"If a solenoid failed in tb-iafe direction and its use was not required during or post accident, no re ment was necessary. If a solenoid was required to function during or post
,.ident, it would be replaced with a qualified solenoid valve, if not already qualified."
During the course of this investigation, numerous telephone calls were made to various suppliers to determine whether they had qualification data on components which were purchased from them. Due to many such verbal reports, a formal written request will be made to the various suppliers.
Since collecting data to meet the response date of this Bulletin took precedence, we have not referenced any official correspondence. The letters are in the process of being prepared now.
Yours truly, 0
D. E. Gilberts Vice President Power Production cc:
Mr. G. Charnoff NRC Office of Inspection and Enforcement Washington, D. C.
Enclosures DEG:nk
9 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEA't CENERATING PLANT Docket Nos. 50-282 and 50-306 LETTER DATED MARCH 13, 1980 RESPONDING TO NRC REQUEST FOR INFORMATION IN IE BULLETIN 79-01B Northern States Power C'epany, a Minnesota corporation, by this letter dated March 13, 1980, hereby submits information in response to NRC request for in-formation concerning IE Bulletin 79-01B.
i This request contains no restricted or other defense information.
l NORTHERN STATES POWER COMPANY By:
D. E. Gilberts Vice President Power Production on this 13th day of March, 1980, before me a notary public in and for said County, personally appeared D. E. Gilberts, Vice President Power Productio.,
and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof and that to the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.
i JEANNE M. HACKER septaav pueLIC. hAIND$$$Of A l
.i HENNEPIN COUNTY l
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