View source for 3F1297-36, Provides Response to NRC RAI on 971202 Re Large Bore Piping & Pipe Support Calculations.Assessment Entitled, Generic Operability Evaluation for Large Bore Safety Related Piping at Crystal River-3, Encl

{{Adams
| number = ML20197B278
| issue date = 12/18/1997
| title = Provides Response to NRC RAI on 971202 Re Large Bore Piping & Pipe Support Calculations.Assessment Entitled, Generic Operability Evaluation for Large Bore Safety Related Piping at Crystal River-3, Encl
| author name = Rencheck M
| author affiliation = FLORIDA POWER CORP.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000302
| license number = 
| contact person = 
| document report number = 3F1297-36, TAC-M99948, NUDOCS 9712230335
| package number = ML20197B282
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 5
| project = TAC:M99948
| stage = Response to RAI
}}

=Text=
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n Florida Power
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87.%",*O u.mn December 18,1997 3F1297-36.
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

==Subject:==
Large Bore Piping and Pipe Support Calculations - Response to NRC Request for Additional Information (TAC No M99948)

==References:==
: 1. NRC to FPC letter, 3N1297-05, dated December 2,1997. Request for Additional Information - Large Bore Piping and Pipe Support Calculations
      -                     2. FPC to NRC letter, 3F1297-33, dated December 8,1997, Plans for Resolution of USI A-46 and Large Bore Piping and Piping Supports
: 3. FPC to NRC letter, 3Fil97-46, dated November 18, 1997, Large Bore Safety-Related Piping Calculations
: 4. FPC to NRC letter, 3F1197-36, dated November 10, 1997 Additional Information for SSFI Items
: 5. FPC to NRC letter, 3F1297-23, dati.d December 4,1997, Licensee Event Report (LER) 50-302/97-040-00

==Dear Sir:==

The purpose of this letter is to provide Florida Power Corporation's (FPC) response to NRC Request for Additional Information (RAI) for large bore piping and pipe support calculations (Reference 1). On December 2,1997, FPC met with the NRC staff to discuss the issues related to large bore piping and piping supports. At that meeting, FPC presented the results of the assessments and proposed actions to address the issues. In addition, FPC provided examples of calculations / analyses of large bore piping and piping supports to support the NRC's ongoing mspection. The resuits of the meeting were documented in FPC's letter to the NRC (Reference 2). FPC also noted that due to the generic aspect of the isrue, FPC issued a voluntary Licensee Event Report (Reference 5).
Attachment A provides FPC's responses to each of the NRC questions. Attachment B provides FPC's assessment entitled " Generic Operability Evaluation for large Bore Safety                      .
Related Piping at Crystal River-3."
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CRYSTAL RIVER ENERGY COMPLEX: 15760 W. Power Line Street a Crystal River. Flortda 34428 6708 - (362) M54486 A Floride Progress Comparey 9712230335 971210 PDR     ADOCK 05000302 P                       PDR     ,

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::*      U.S. Nuclear Reguictory Comm8ssion
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* 3F1297-36.
Page 2 of 2 There are no commitments made in this letter. -If you have any questions regarding this letter, please contact Mr. David Kunsemiller, Manager, Nuclear Licensing at (352) 563-4566.'
Sincerely,-
M,W. Rencheck, Director Nuclear Engineering and Projects
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                ' Attachments                                                                                  >
e ..             xc: Regional Administrator, Region !!
Senior Resident Inspector NRR Project Manager Kamal A. Manoly, NRC-NRR
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v      g t       ~ U.S. Nuclear Regulatory Commission                                                Attachment A 3F1297-36                                                                              Page 1 of 3 Response. to NRC RAI La ge Bore Pipine and Pipe Support Calculation _s NRC Ouestion 1 Describe any assessment or piping system analysis that may have been performed to address the concerns identified in the Wais Report. Specifically, describe examples of evaluations that you performed to determine that, notwithstanding the Wais findings, the piping systems are still capable of performing their safety functions.
FEC Response FPC has conducted an Operability Evaluation (OE) which contains the assessment that addresses the operability of the large bore piping and the concerns identified in the Wais Report. This OE provides the basis for addressing the NRC questions, and is included as Attachment B to this submittal.
NRc. ouestion 2 On Page 2 of Attachment D to your {{letter dated|date=November 10, 1997|text=letter dated November 10, 1997}}, you indicated tb:"
specific portions of piping systems have been requalified or evaluated in the recent past. You also stated that while a number J code compliance issues have been identified over the years, subsequent assessments and analyses have not identified a piping system that was incapable of meeting its design basis requirements.          Furthermore, some of the qualification efforts addressed issues that are similar to those discussed in the Wais Report. You also stated that no items were found to represent an operability concern and, where code compliance concerns were identified, they were promptly corrected. Discuss the basis for your assertions that no items were found to represent an operability concern. Your discussion should be supported by examples of assessments or analyses of piping system in the as-found condition (and as corrected, if apprcpriate) relating to any of the areas identified below.
: a. Modeling of rod hangers in the piping seismic analysis, and potential for uplift.-
: b. Effects, on the pressure boundary integrity of piping, of the combined effects of pnmary stressas and secondary stresses, due to integral attachments, c,     Capacity of non standard anchors against the seismic loads indicated by existing a talysis,
: d. Safety margins of uncinched U-bolts, used as two-way restraints, against published design values for U-bolts under biaxial (tension / shear) loadings.

c.
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                 = U.S. Nuclear Regulatory Commission Attachment A 3F1297 36 =                                                                               Page 2 of 3        y  ,
                 ; c.       Effects of snubber activation on supports consisting _of dual snubbers.                               i If.        Consistency of damping values used in CR-3 seismic piping analyses with those specified in ths FSAR.
: g.    ' Reliability of supports involving strut / snubber angularity.
J           Impact of CR-3 overlap criteria on II/I concern.
: 1.       Modeling of spring hangers in the seismic piping stress analysis.
L:              - j.        Use of axial trunnion supports on elbows, which may induce local stresses on the pipe'as a result of friction developing between the contact surfaces,
: k. 1 Modeling of valves in the seismic piping stress analysis, and the determination of valve Jacceleration used in seismic qualification.
[.               L 1.       Consideration of seismic anchor motions (SAMs).
FPC Response to Ouestion 2 The attached assessment, " Generic Operability Evaluation for large Bon Safety Related J                - Piping at Crystal River-3," addresses the issues raised by the NRC, and more specifically each                ,
i of the subparts of question 2 as follows:
: a.            See Sections 4.1, 5.1, 6.1 of the OE. - Examples of past evaluations are provided in Attachment A of the OE.
b/            See Sections 4.2,5.2, and 6.2 of the OE. This subject is grouped with axial trunnion supports on elbows since the' concern here is welded attachment stresses. Examples are provided in Attachment A of the OE.
                ; c.             See Sections 4.4,5.4, and 6.4 of the OE.
7
                 ; d.            See Sections 4.5,5.5, and 6.5 of the OE. - Examples are provided in Attachment A of 4                                the OE,                                                                                           i Le.             See Sections 4.6,~ 5.6, and 6.6 of the OE = This is not an operability concern.
: f.            See Sections 4.7,5.7, and 6.7 of the OE.
i g.            $ Gee Section 4.3,' 5.8, and 6.8 of the OE. - Examples are provided in Attachmem A ef
.                               - the OE.
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:?              -_U.S. Nuclear'Regul: tory Commission'-
Attachment Ai           -
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: 3F1297-36 J                                                                                  Page 3 of 3 -                ,!
:                             hr   - See' Sections 4.12, 5.12, and 6.12 of the _OE. Examples are provided in Attachment :                              )
A of the OE.
1 1.1  LSee Sections 4.9, Sa'; and 6.9 of the OE This is not an operability concern.'
                                                                                          ~
j.-. See Sections 4.2,5.2,' and 6.2 of the OE I This subject is grouped with axial trunnion --
supports on elbows since the concern here is welded attachment stresses.- Examples-are provided in Attachment A of the OE.                                                                       .-
k.-    See Sections 4.10,5.10, and 6.10 of the.OE. Examples are provided in Attachment                                   +
i-                                   A of the OE as well as a generic evaluation of valves for applied accelerations in Section 6.10.
                           ; 1.     --See Sections 4.11,5.11, and 6.11 of the OE. This is not an operability concern.
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