ML20087M118
| ML20087M118 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/23/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8403290026 | |
| Download: ML20087M118 (6) | |
Text
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ol 400 Chestnut Street Tower II March 23,1984 Director of Nuclear Reactor Regulation Attention:
Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Comission Washington, D.C.
20555
Dear Ms. Adensam:
In the Matter of
)
Docket No.
50 -327 Tennessee Valley Authority
)
Please refer to my letter to you dated November 14, 1983 which mquested an extension of the completion chte of the requirements of 10 CFR 50.49(h) for the Sequoyah Nuclear Plant unit 1.
In accordance with the request of Carl Stahle of your staff, we are enclosing a new listing of Category IV components which will not be replaced or mlocated by the ed of the second refueling cycle as per the 10 CFR 50.49 (h) requirement. This new listing provides the reasons and/or problems associated with these components not meeting the scheduled comitment. We are presently tracking 408 category IV components for Sequoyah unit 1.
Seventy-eight of the unit 1 components have been replaced or relocated. A total of-164 components will be dispositioned during the current unit 1 reftleling outage. Of the remaining 166 components, 67 of these can be dispositioned during the nonoutage period following the present mftneling outage and will be scheduled for completion before March 31,1985, but will be completed no later tnan the cycle 3 refueling outage. The remaining 99 components cannot be scheduled for the present reftseling mtage and can only be dispositioned during an outage. These components will be diepositioned during outages of sufficient duration er during the unit 1 cycle 3 refueling outage now scheduled for June 1985. In addition, it has been TVA's policy that modifications will not be performed during a reftzeling outage unless all the equipment is at the site and documentation is complete 30 days before the start of the outage. In view of this, we are requesting an extension to June 1985 for 166 components.
Depending on the delivery of equipment and documentation requirements, we will attempt to complete the 67 items which can be worked during nonoutage.
I periods before March 31, 1985. For information, we are tracking a total of 899_ category IV components for Sequoyah units 1 and 2.
One hindred and seventy-four of the components have been replaced or relocated.
i 8403290026 B40323 i
DR ADOCK 0500032 I
i 1983-TVA SOTH ANNIVERSARY j
An Equal Opportunity Employer.
1 J
. Director of Nuclear Reactor Regulation March 23,1984 If you have any questions concerning this matter, please get in touch with K. P. Parr at FTS 858-2685.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, hmger Nuclear Licensing hi y of 98 Gaubh N 4Has
~
Notary Public My Consnission Expires
'[-
Enclosure cc:
U.S. Nuclear Regulatory Commission (Enclosure)
Region II Attn:
Mr. James P. O'Reilly Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
ENCLOSURE Listed below are the components tabulated by nonconformance report (NCR) i number with the reason (s) for their not meeting the performance date. The components which can be dispositioned during nonoutage periods are denoted with an asterisk (*).
I NCR MEB 8201 - Atteapts to qualify the operators for the valves listed under this NCR continued until June 1983. Final disposition was made at that time. These operators were supplied with type
'B' insulation
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which would not meet the necessary requirements.
It was determined that operators with type
'F' insulation would be necessary. Emergency procurement was initiated on June 7,1983. On November 14,1983, a hold order was placed on the vendor by our Office of Quality Assurance (QA)(Audit QDBVA-84-5). The hold order has been removed as of February 27, 1984, but any shipments received will be too late for installation during unit 1 cycle 2 outage. The QA deficiency was reported to NRC Region II for Watts Bar Nuclear Plant and Bellefonte Nuclear Plant on December 15, 1983. The vendor has been contacted and is to provide a firm delivery date by March 1984. Replacement of this equipment will fall outside the present unit 1 refueling outage, but work will be completed no later than the end of the next refueling i
outage. If an outage of sufficient duration occurs after equipment is received, this NCR will be completed prior to the next refueling outage. We have also determined that 22 of these components can be modified during nonoutage periods and will be scheduled for completion before March 31, 1985, but will be completed no later than the cycle 3 refueling outage.
The following valves are covered under this NCR.
FCV-7 0 - 2, 3, 4, 8, 9 *, 10*, 13 *, 23 *, 2 5 *, 26 *, 27 *, 64*, 7 4*, 7 5, 92, 13 9, 140, 143 *, 153 *, 156 *, and 16 8*.
FCV 81, 82, 83, 88, 91, 96, 99, 104, 107, 109, 112, 123 *, 124*,
125*, 126*, 127*, 128*, 146*, 147*, 223*,
NCR MEB 8007 - Final disposition of this NCR was not made until July 1983, due to efforts to qualify the equipment by test and analysis.
Emergency procurement'was initiated for the following equipment but could not be received in time for the second refueling of unit 1 at Sequoyah. These solenoid valves were rated for 77 degrees Fahrenheit and could be subjected to ambient temperatures of 1104 degrees Fahrenheit during accident environment conditions. However, this equipment is now scheduled to be arriving at the site, up through September 1984. In addition, we have determined that 24 of the components listed below can be modified during nonoutage periods.
These components will be scheduled for completion before March 31, 1985, but will be completed no later-than the cycle 3 refueling outage. The remaining components will-be modified no later than the next refuellag outage.
FSV 30 - 23, 50, 70, 8, 93, 10, 12', 140, 15, 160, 17, 193, 200, 37D, 40, 50, 51', 52, 53', 54', 56, 57', 58', 59*, 618, and 625 FSV 65 - 8' and 518 The operators for the control valves under this NCR are also from the vendor on which a QA hold has been placed (see NCR MEB 8P01). The following components sre affected.
FCV 72 - 28, 20, 21, 22, 23, 39', 40', 418 FCV 3 - 33, 47, 87, 100.
LCV 62 - 136 NCR EEB 8014 - This equipment, the hydrogen monitoring system, was classified as mquired to operate in a postaccident environment.
Documentation was not available to ensure its operation under these conditions; therefore, efforts were mde to qualify by testing.
In May 1983, it was determined that the entire unit could not be qualified. Efforts were made to mlocate it to a mild environment, but it was not feasible to miocate the entire system. A revision to the NCR was issued in October 1983 to relocate only the components which could not be qualified. By this time drawings could not be revised in time to schedule the revision for the unit 1 cycle 2 outage. These drawings are now complete, and this modification will be scheduled for the next outage of sufficient duration and will be completed no later than the next mfueling outage. The following instruments' relocations were delayed.
FIC-43-200A, FSV-43-200A, PDCV-43-200A, PS-43-200A, FIC-43-200B, FSV-43-200B, PDCV-43-200B, PS-43-200B, FSV-43-200D, PS-43-200D, FSV-43-2003, FSV-43-200E, FSV-43-2000, FSV-43-200H, FIC-43-210A, FSV-43-210A, PDCV-43-210A, PS-43-210A, FIC-43-210B, FSV-43-210B, PDCV-43-210B, PS-43-210B, FSV-43-210D, PS-43-210D, FSV-43-210E, FSV-43-210F, FSV-43-2100, FSV-43-210H NCR NEB 8157 - These system 68 (reactor coolant system) items listed below were dispositioned on July 12, 1983, to be replaced, and the purchase request was initiated September 1983. These items are also from the vendor on which a QA hold order has been placed (see NCR 8201). As stated earlier, the QA hold order has now been released and the vendor' is to supply firm delivery dates by March 1984. This equipment will be modified no. later than the next refueling outage.
FCV-68-332, 333 FCV-63-172 NCR MEB 8301 - The manufacturer attempted to qualify the required temperature switches until August 1983; therefore, dispositioning of this NCR did not occur until August 1983 Expedited delivery of the switches was originally scheduled for February 24, 1984. These items
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0 were also pitced 'on hold by QA. This hold ordsr htc now been rels: sed and the vendor _ has been contacted to. provide a fire delivery date. We have also determined' that this equipment can be modified during-nonoutage periods and will be scheduled for dispositioning during the j
period following this mfueling outage but will be completed no later i
i than the cycle 3 refueling outage. The following switches are affected.
TS-30-1868, 187', 1908, 1918, 194', 195', 1968, 1978, 201e, and 2028 l
HTR-30-147A on this NCR was requisitioned in August 1983, with a l
delivery date of September 7,1984. The requisition was delayed to adequately define the interface requirements. The NCR was just i
resolved and replaces the control components and not the heater elements which are not affected by radiation. This modification will l
be scheduled for no later than the next refueling outage.
1 NCR EEB 8036 - Final disposition of this NCR was not made until June 1983. Emergency procurement was initiated with a delivery date of March 1984 These components are now onsite and can be installed during nonoutage periods; themfore, these items will be scheduled for modification during the nonoutage period following the present refueling outage but will be completed no later than than the cycle 3 refueling outage. The following components are affected.
s FS-30-1948, 1958, 1968, and 1978 f
NCR EEB 8009 - Noh difficulty was experienced in finding qualified j
replacements for these heating and ventilating (System 30) differential pressure switches. A redesign was mquired to incorporate pressure switches instead of pressure diffemntial j
switches. After an acceptable vendor was located and procurement initiated, the vendor was placed on QA hold because of inadequacies in their QA program. This hold was released December 19, 1983 The earliest delivery date is April 1,1984. These components will be installed during the next outage of sufficient duration once they are i
received, or no later than the next refueling. outage. The following t
components are affected.
l PS-30-46A and B, PS-30-47A and B, PS-30-48A and B.
NCR MEB 8008 - The system 3 (auxiliary feedwater) motor, MTR-3-128, was qualified September 1983 (Re: EEB 830623 931); however, it was determined that a heater should be installed to msure the motors remain qualified. These heaters were to prevent accumulation of condensation within the motor. It has now been determined that.
periodic rdnning of the motor will accomplish the same results; J.
therefore, these heaters are no longer mquired and these items have
' been deleted from the category IV replacement' schedule.
t,
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.NCR EEB 8303 cnd EEB 8004 - The c:ven comp:nents licted below were requisitioned August 16, 1983, after the resolution of the NCRs.
Before the quote was received frem the vendor, there was a d1ange to the requisition requiring a double pole switch instead of single pole switch for fbur of the seven components. This revision was caused by
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I a d1ange in the evaluation of the environmental conditions.
Acceptance of the contract was made on December 2,1983, with a twelve week perfbrmance date that was later changed to March 30, 1984. The s
delivery is too late for scheduling and planning purposes for the present unit 1 cycle 2 outage; however, these items can be installed j
i during unit outage periods and will be scheduled for changeout as soon as possible, once they are received at the site, but will be completed no later than the cycle 3 refueling outage. The following components are affected.
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PS-3-121 A', B', D' PS-3-160A', 160B'-
PS-3-165A*, 165B' NCR NEB 8104 - These components were initially identified as status I equipmen t.
Late in our review it was determined that we did not have proper documentation to prove qualification to NUREG 0588. We attempted to gain qualification documentation through Westinghouse.
We contracted with Westinghouse to provide us with an analysis and
. qualification data to meet 0588 with the existing motor brakes. In late 1983, Westinghouse determined that the existing brakes could not be qualified. Final disposition of this NCR has now been made to replace the existing brakes with qualified ones. A vendor has been selected and a request fbr PLrm delivery dates has been processed.
Vendor response is now expected by March 1984. These modifications will be performed during the next outage of sufficient duration, once the components are received, but no later than the next refueling outage.
The following valves are affected.
FCV-62-63, FCV 1, 5, 6, 7, 8, 11, 47, 48, 72, 73, 93, 94 FCV-74-33, 35 LCV-62-132, 133, 135, 136, 138 NCR EEB 8105 - This equipment is onsite and was originally scheduled for the unit 1 cycle 2 refueling outage; however, we are unable to work these items due to lack of time for preparation, therefore, these items will be scheduled for the next refueling outage or.next outage of sufficient duration. The following components are affected.
4 FCV-43-2, 11, 22, 34, 75 i
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