View source for B11959, Forwards Rev 0 to EMD-054460, Seismic Evaluation of Nonseismic Category I Piping in Seismic Category I Bldgs. Nonseismic Category I Piping Will Not Adversely Affect Seismic Category I Piping

{{Adams
| number = ML20137M052
| issue date = 01/14/1986
| title = Forwards Rev 0 to EMD-054460, Seismic Evaluation of Nonseismic Category I Piping in Seismic Category I Bldgs. Nonseismic Category I Piping Will Not Adversely Affect Seismic Category I Piping
| author name = Mroczka E, Opeka J
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = Noonan V
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000423
| license number = 
| contact person = 
| document report number = B11959, NUDOCS 8601280174
| package number = ML20137M058
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}

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                    .v,      a       "s.acw w.                                      P O. DOX 270 x,w ..rt. -wa w-HARTFORD. CONNECTICUT 06141-0270 L   L   a CC' C',717',". -                                                  (2031 665-5000 January 14, 1986 Docket No. 50-423 B11959 Director of Nuclear Reactor Regulation Attn:     Mr. V. Noonan, Director PWR Project Directorate #5 Division of PWR Licensing - A U. S. Nuclear Regulatory Commission Washington, D. C. 20555

==References:==
(1)   3. F. Opeka letter to B. 3. Youngblood, Seismic Interaction Program, dated October 31,1985.
(2)   B. 3. Youngblood letter to 3. F. Opeka, Supplement 4 to NUREG-1031 - Millstone Nuclear Power Station, Unit No. 3, dated December 6,1985.
(3)   3. F. Opeka letter to 'V. Noonan, Status of Seismic Interaction Program, dated December 20,1985.
(4)   V. Noonan letter to 3. F. Opeka, Seismic Interaction Program, dated December 24,1985.
(5)    3. F. Opeka letter to V. Noonan, Seismic Interaction Program, dated January 6,1986.

==Dear Mr. Noonan:==

Millstone Nuclear Power Station, Unit No. 3 Seismic Interaction Program In Reference (1), Northeast Nuclear Energy Company (NNECO) provided the Staff information regarding the seismic interaction program for Millstone Unit No. 3. The seismic interaction program consists of three distinct tasks:
o        Demonstrate the adequacy of equipment anchorages for non-seismic equipment in seismic Category I buildings.
o         Demonstrate the structural integrity of piping and supports for selected subsystems.
o         Perform walkdowns to identify swing / sway interactions between non-seismic Category I piping and equipment and seismic Category I piping and equipment.
In Reference (2), the Staff concluded that the Millstone Unit No. 3 seismic g
interaction program met the relevant requirements of GDC-1 and 2 and G601200174 860114 PDR    ADOCK 05000423 i
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P                            PDR

10CFR100 Appendix A and was acceptable. However, the Staff included a license condition which requires NNECO to complete the implementation of the seismic interaction program including corrective actions before the unit exceeds 5% power. In Reference (3), NNECO provided the Staff the status of th implementation of the seismic interaction program for Millstone Unit No. 3. In Reference (4) NNECO submitted a preliminary report on the seismic interaction program for Millstone Unit No. 3.
As discussed in Reference (3) the review of equipment anchorage has been completed and modifications have been issued. These modifications will be completed prior to the unit exceeding 5% power operation.
All plant walkdowns to identify swing / sway interactions were completed and modifications were issued (105 inside containment and 115 outside containment).
All modifications inside containment are complete. The level of completion outside containtaent is 50% and will be 100% prior to the unit exceeding 5%
power.
The structural integrity of piping and supports for selected subsystems has also been demonstrated. As committed in Reference (5), NNECO hereby submits the final report which addresses the adequacy of piping and pipe supports up to the building structure attachment point (Enclosure 1). Enclosure 2 is a summary of the anchorage reviews performed by NNECO. There are no unacceptable findings in this task and no modifications are required. The generic concern raised in Enclosure 1, regarding sliding supports has been addressed in the seismic interaction walkdowns. Sliding supports which could not accommodate six inches of pipe movement and could cause unacceptable interactions should they fail, were modified. These modifications are included in the 220 mentioned above and will be complete prior to the unit exceeding 5% power operation.
In conclusion, the seismic interaction program demonstrates that there is reasonable assurance that non-seismic Category I equipment and piping will not adversely affect the ability of seismic Category I equipment and piping. to perform their. safety functions. This final report should fully resolve the Staff's concerns contained in Reference (2) and satisfy License Condition 2.C(4) of the Millstone Unit No. 3 Operating License, NPF-44.
If there are any questions, please contact our licensing representative, directly.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY et. al.                                       ,
By NORTHEAST NUCLEAR ENERGY COMPANY Their Agent g
T, _7 UpFic TV 1
J. F. Opeka Senior Vice President By: E.'JQi oczka Vice Presi ent
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i Then personally appeared before me E.J. Mroczka, who being duly sworn, did                                                                     -
]                state that he is Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing l                information in the name and on behalf of- the Licensees herein and that the statements contained in said information are true and correct to the best of his l                knowledge and belief.
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