ML20127J401
| ML20127J401 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, Zion  |
| Issue date: | 01/15/1993 |
| From: | Jackson M COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, TAC-M69442, TAC-M69443, TAC-M69476, TAC-M69477, NUDOCS 9301250127 | |
| Download: ML20127J401 (19) | |
Text
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1
. f I. I Commonwealth Edison 1400 opus Place January 15,1992 Downers Grove, Ilknots 6051E Dr. Thomas Murley, Director U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Subject:
NRC Evaluation of the Commonwealth Edison Response to Generic Letter 87 02, Supplement 1," Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors", SQUG Resolution of USI A 46.
Dresden Nuclear Power Station NRC Docket 50 237/249 and TAC M69442/69443 Ouad Cities Nuclear Power Station NRC Docket 50-254/265 and TAC M69476/69477 Zion Nuclear Power Station NRC Docket 50-295/304 and TAC M6949P/69493
References:
(1)
SOUG Response to GL 87-02 dated August 21,1992 to J.G.
Partlow from N.P. Smith (2)
Commonwealth Edison res onse to GL 87-02 dated September 21,1992 to Dr. T. E. Murl from M. A. Jackson.
(3)
NRC Safety Evaluation of ommonwealth Edison's response to GL 87-02 dated November 20,1992 to T. J. Kovach from C. P. Patel.
Generic Letter.87 02, Supplement 1 recuired that each licensee: 1) either commit to use both the SOUG commitments and the implementation guidance or provide an alternative method,2) provide an implementation schedule to implement GIP-2,
- 3) provide detailed information on procedures and criteria used to generate the in-structure response spectra and 4) infomi the staff if they intend te change their licensing basis tc reflect a commitment to the GIP methodology for verifying seismic
. adequacy of mechanical and electrical equipment, prior to receipt of tne staff's plant-
=
specific safety evaluat;on to resolve USI A-46.
Commonwealth Edison's submittal to Generic Letter 87-02, Supplement 1 was provided in reference 2. The Nuclear Regulatory Commission's (NRC) safety evaluation of the CECO submittal was provided in reference 3. The purpose of this letter is to provide a response that addresses the NRC staff's questions presented in reference 3. Specifically, this response provides the foUcwing; 1) a clarification of CECO's coramitment to the SCsmic Qualification Utility Group (SOUG) commitments and tne implementation guidance as
~
described in the Generic Implementation Procedu e, revision 2 (GIP-2), and 2) the requested additionalinformation regarding the in-Structure Response Spectra (ISRS) for Dresden and Quad Cities stations.
2100GJ-93o125o127 930115 PDR ADOCh 05o00237 O
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P pop ZNLD/2461/1
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'I The NRC safety evaluation found that the CECO responses regarding the ISRS for Zion.
station, and the implementation schedules for the three USl A-46 CECO plants,-
Dresden, Quad Cities and Zion stations are acceptable. However, the NRC staff stated that the response was unclear as to whether CECO intends to use both the SOUG commitments and the implementation guidance. The staff did interpret our response as a commitment to the entire GlP 2 including both the SOUG commitments and the Im alementation guidance, and therefore, considered it acceptable. In the original su amittal CECO committed to the GIP, in its entirety, including clarifications, interpretations, and exceptions identified in SSER-2 as clarified in the reference (1)
August 21,1992 letter with no exceptions.
)
For purposes of further clarification, CECO will use Part I, Section 1.3 of the GIP, j
revision 2 with regard to full implementation of all provisions of the guidance sections.
Additionally, as the staff has suggested, for implementing the GIP-2, CECO will not merely follow the August 21,1992 SQUG letter but also will follow the Attachment to the safety evaluation (reference 3), which is the staff's response to the SOUG August 21,1992 letter.
The NRC requested additionalinformation regarding the Dresden and Quad Cities in structure response spectra. This information is enclosed in the Attachment to this letter.
As indicated in the original submitta! (reference 1), the current schedules may be affected by coordination with the seismic IPEEE response, the completion of the SOUG training, significant outage schedule changes, and the availability of industry resources committing to sup aort the large number of licensees implementing this arogram. The current approved mplementation schedules are also dependent upon tie NRC Staff approval of the enclosed in-structure response spectra (ISRS) for Dresden and Quad Cities stations. Accordingly, please provide your acceptance of the ISRS by March 15, 1993.
If you have any questions regarding this letter, please contact me at (708) 663-7287.
Resp ctfully,
/
1 1/
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Marc'a A. Ja son r
Nuclea(Generic ssues Licehsin r dministrator i n ue %
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A. B. Davis. Regional Administrator, Rlll
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{T[tT J. Dyer, Project Director, NRR (raAsyEttEN D: LONG B. Siegel, Dresden Project Manager, NRR We Puem mn er aus C. Patel, Ouad Cities Pro!ect Manager, NRR m cemS$10N EVES : EnV93 C. Shiraki, Zion Project Manager, NRR
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W. Rogers, Dresden SRI p-fit <73 T. Taylor, Quad Cities SRI J. Smith, Zion SRI ZNLD/2461/2
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ADDllLORALillfE1LAllM3 Luc 1TEC.113LRLSE011SLSEffLM f.QERESDffl - UtilT5 ? & 3 At10_0'LACLClllLS - URL1LLL2 1.
ln!rMadion Dresden and Quad Cit;es are considered sister plarts, with very similar structural arrangemen:s, situated in the same seismological province 1
l with very similar eart0guake history and similar rock foundations.
As stated in Commonwealth sdison Company's (CECO) letter dated September 21, 1992 to the NRC, two of the most comprehensive and recent studies for seismic risk at nucleir power plant sites, located east of the Rocky Mountains, have been performed by Lawrence Livermore Lab (LLL) and 4
Electric Power Research Institute.. The LLL study was sponsored by the
- NRC, Both studies showed that, in terms of uniform hazard spectra and probability of exceedance of oect ground acceleration. Quad Cities has a slightly lover seismic risk tLan that of Orescen, 1
Based on the above, CECO believes that the SSE ground motion at Quad Cities should be the same at Drec. den, if not slightly lower. However, in deference to thp position stated in your let*?r dated November 20, 1992, CECO will use the higher peak ground acceleration (PGA) of 0,24g for Quad Cities - Units 1 & 2.
The followinq sections describe the ground response spectrum, time history, building models and damping value used for in-Structure Response Spec tra (ISRS) generation for both Dresden and Quad Cities stations.
I1, Stound Reingnielpedr,um The site. specific SSE spectrum anchored at 0.139 has been aoproved for Dresden Unit 2 under the Systematic Evaluation Program (SEP) by the
- NRC, However, for the resolution cf USl A 45 Commonwealth Edison Company (CECO) will use the conservative design basis SSE ground
?
spectrum anchored at 0,29 The Dresden design basis SSE ground response spectra are smoothed Housner type spectra, Figure 1 shows Housner type response spectra, for various damping values,-anchored-to 0,109 PGA, The 5% damped ground response spectrum, anchored to 0.20g PGA, will be used for A-46 work on Dresden - Units 2 & 3.
At Guad Cities Units 1-&
2, the ground spectrum to be used for A 46 work wil1 be of the same shape as for Dresden (shown in Figure 1); however, it wil_1 be scaled up
+
by anchoring at 0.249 i
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9 111, lig History Used for_lnrStructure Responsa_ Spectra (ISRS) Generation'
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I The design-basis ISRS for Dresden Units:2 & 3 were generated using a_
time history method of analysis.
El. Centro 1940_ earthquake -N S component, anchored to 0.10g was used to_ generate the ISRS-for OBE.
For-SSE design, the: spectral values were obtained by doubling the OBE spectra (St.e also Section VI below).
A comparison-of the design ground spect
-.o and the spectrum of El. Centro 1940 earthquake N-S component, both anchored to 0.109. is shown in Figure 2.
It can be seen that the El. Centro N S component envelops the design ground spectrum quite; a
conservatively for most of the frequencies.
IV.
Buildina Model Used for ISRS Gfatta110.D The building models used for Dresden - Unit 2 & 3 ISRS generation :are =
shown in Figures 3 & 4 for N-S and E W directions..respectively.
The.
mass and stiffness properties are also shown in the above figures.
The Quad Cities Units 1 & 2 were designed as sister units to Dresden -
Units 2 & 3 by the same NS$$ supplier, using the same architect / engineer. A review of the plants structural drawings for parameters which affect the seismic models (i.e.
mass and stiffness) has confirmed that the two plants are quite simiiar in terms of their seismic behavior.
The review included comparison of building dimensions. major floor slab elevations. plan dimensions thickness of slabs and. concrete walls, and. steel bracing dimensions which constitute to the horizontal stiffness of the buildings.
Based upon this comparison between the two plant's seismic building-characteristics.
CECO has_ concluded that the building model used at Dresden is acceptable to be used for Quad Cities.
Since both the plants are founded on rock, there is no soil structure interaction effect considered, The mathematical models shown in Figures-3 & 4 represent the combined reactor-turbine building complex.
The buildings and models are described Driefly in the following paragraphs.
For both plants the reactor buildings are made up_of a_ reinforced concrete structure supporting a steel superstructure and roof.
The concrete portions of-structures begin at the foundation located-approximately 41 feet below grade and extend to'approximately 95 feet above grade.
The steel superstructure is supported on top of: the-concrete structure and extends to the'rtof located approximately 1411 feet above grade.
For both plants the turbine buildings are also made up of-afreinforcEd concrete structure supporting a steel superstructure and roof.
The concrete portions of structures begin approximately at grade and extend to about-44 feet above grade.
The. steel structure begins at about 44 feet above grade and_ extends to the turbine building roof approximately 105 feet above grade, ti Page 2
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For the dynamic response analysis, an equivalent-lumped mass model was developed for the buildings in each direction, in the N-S direction, the reactor and turbine building models are connected at two points 1 9
(1) at about 44 feet above grade, representing the operating floor of the turbine building: and (2) at about 105 feet above grade, representing the roof of the turbine building in the E-W direction, I
the two building models are connected at one oint'only, at about 44 feet above grade representing the operating f cor of the turbine building.
Each story level mass represents the mass'of concrete and equipment at each floor and the tributary mass of the equipment and concrete walls between adjacent floors. -The top story r.iasses are-similarly developed but include the tributary mass of the walls,-Steel frame, and the mechanical equipment of the stcry.
The average area and' moment of inertia of the structural elements between floors is used to -
determine the stiffness characteristics between masses.
q The-lines interconnecting the masses in Figure 3 represent weightless N-l S springs having a stiffness equal to the stiffness of the actual structure in_that direction.
Likewise, the lines in figute 4 represent E-W springs having a stiffness equal to tne stiffness of the actual structure in that direction, V.
Qdmoina Value3
+
A 5% modal damping value was used in the time-history analysis of the building model, This damping value is-consistent with the Operating.
Basis Earthquake (0BE) level.
No separate building analysis was done with higher damping values corresponding to SSE: the ISRS. generated for OBE were conservatively doubled for use in SSE design.
VI.
Jn-St ruf.luleJlf.10.2nie 5 o e c t e a The original horizontal ISRS for Dresden - Units 2 & 3 were generated for OBE, only for 0.5% spectral damping value.
The ISRS for SSE design were obtained by dcubling the OBE ISRS.
Subsequently, the horizontal design response' spectra for additional damping values of 1%. 2%, and Si for both the OBE and the SSE were-generated.
Synthetic time histories consistent with the 1/2% damping original unwidened spectra were obtained for eacn floor elevation by iterations using the El._ Centro 1940 N-S earthquake record as the i.
starting point.
A typical comparison of'the synthetic: time history
-response spectrum and the original unwidened response spectrum is shown in Figure 5.
These synthetic time histories-were then used to generate OBE and-SSE response spectra.
The peaks of the spectra.were widened by 15% on each side, Typical SSE in structure response spectra are shown-in Figures 6 through 13.
Since these-lSRS were generated using conservative time history and damping values, for A 46 work, they (the 5% damped spectra)'will be used as ' conservative, design' ISRS as defined in GIP-2.
For Quad Cities, the ISRS will be obtained by scaling up the 5% damped Dresden lSRS for SSE by a factor of 0:24 /0.29, which is the ratio of 9
Ouad Cities SSE PGA to Dresden SSE PGA, and used as ' conservative, design' spectra for A 46 work. An example of such a-spectrum obtained-by scaling the 5% damped Dresden ISRS (Figure 12) by'a factor of 1.2 is shown in_ Figure 14, i;
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