ML20207N559
| ML20207N559 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/12/1987 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Harold Denton, Tam P Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20207N561 | List: |
| References | |
| 2NRC-7-004, 2NRC-7-4, TAC-64378, NUDOCS 8701140288 | |
| Download: ML20207N559 (7) | |
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2NRC-7-004 Beaver Valley No. 2 Unit Project Organization Telecopy (41 64 5 Ext.160 S.E.G. Building P.O. Box 328
.Ianuary 12, 1987 Shippingport, PA 15077 Mr. Harold R. Denton Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. Peter Tan, Project Managcr Division of PWR Licensing - A Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Final Safety Analysis Report - Amendment 13 Gentlemen:
Duquesne Light Company, acting on its own behalf and as agent for The and The Toledo Clevelano Electric Illuminating Company, (Ohio Edison Company,3) signed originals plus Edison Company, is filing herewith three copies of Anendment 13 to the Final Safety Analysis Report (FSAR) for the Beaver Valley Power Station Unit No. 2.
Attachment #1 provides a brief description of FSAR changes in this amend-ment which we believe could impact the staff's Safety Evaluation Report.
Attacnment #2 provides a listing of tests in this amendment which are no longer included in the Initial Test Progran described in the FSAR.
Attachment #3 provices a list of FSAR changes in this anendment which address itens related to the Stone and Webster Engineering Corporation (SWEC)
Engineering Assurance Audit No. 52.
This infonnation is being provided in accoraance with the request made by the NRC Office of Inspection and Enforce-ment during the exit meeting of their final inspection of audit results and corrective actions on Septenber 25, 1986.
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United States Nuclear Regulatory Commission Mr. Harold R. Denton, Director Final Safety Analysis Report - Amendment 13 Page 2 Please insert the revised Amendment 13 material into the FSAR as per the Amendment Instruction Sheet.
DUQUESNE LIGHT COMPANY By Sr i
Pr den RWR/iJr NR/ AMEND /13 t
nents cc:
E. Imbro, Section Chief, QA Branch, IE (w/a)
H. Wang, Inspection Specialist, QA Branch, IE (w/a)
United States Nuclear Regulatory Commission Mr. Harold R. Denton, Director Final Safety Analysis Report - Auendment 13 Page 3 COMMONWEALTH OF PENNSYLVANIA )
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COUN W OF BEAVER
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, before me, a On this day of<
Notary Public in and for said Iommonwealthfa$d County, personally appeared J. J. Carey, who being duly sworn, deposed and said that (1) he is Senior Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statenents set forth in the Submittal are true and correct to the best of his knowledge.
/L(CUk}'-(LW' Notary Puolic sHEllA N. FAngef. NORD 56mc SNIPPIASP0ff SON, BEAWR C8em M 88MN885t f3 Plats SCT. n 1ses h W Assedaties etseamen
Attachnent #1 l
Description FSAR Sections Changed SER Sections Affected Differential Settlenents 2.5.4.10.2 2.5.4.3.3 2.5.4.13 2.5.4.5 l-Internal Flooding 3.6B.1.3 3.6 Analysis Pipe Break Criteria 3.6B.1.3, 15.6.2.1 3.6 T1.9-1, T1.9-2 I
Jet Impingenent Analysis 3.6.B.2.3 3.6 I
Quench Spray and 6.2.2.3.1 6.2.2 Recirculation Spray T.6.5-4, T.6.5-5 6.5.2 F.6.5-1 Post LOCA Operator T.6.3-7 7.3.2.1 Actions for Hot Leg t
Recirculation New Fuel Storage Area 9.1.1.2 9.1.1 9.1.1.3 L
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Attachment #2 14.2.12.7.1 Computer Input and Printout Data Test (S0V) 14.2.12.52.4 Containnent Instrument Air Design Verification (S0V) 14.2.12.54.1 Nonnal AC Power Distribution Test (50V) 14.2.12.72.1 Seismic Instrumentation Test (SOV) 14.2.12.81.1 Site Security System Test (S0V)
The above testing is redundant to the testing already canpleted by the Startup Proof Test Group.
14.2.12.2.10 Rod Cluster Control Assembly Pseudo Ejection Test at Zero Power (IST) 14.2.12.2.11 Static Rod Cluster Control Assenbly Drop Test at 50 percent Power (IST) 14.2.12.2.14 Rod Cluster Control Assembly Pseudo Ejection Test at Power (IST)
Beaver Valley Pcwer Station Unit 2 and previous Westinghouse three loop core designs are similar.
These sim.ilarities coupled with the extensive design code and accident analysis validation which has occured during other three loop startups supports this action.
14.2.12.2.9 Rod Cluster Control Assembly Bank and Boron Worth Measurement (IST)
The Rod Swap niethod for measuring rod worth will be used instead.
(Test abstract 14.2.12.4.4 Low Power Physics Test was revised to show this).
14.2.12.8.11 Reactor Vessel Internals Inspection Refer to response to Open Iten 9 of the SER in Letter 2NRC-6-081, August 8, 1986.
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Attachnent #3 Action Item FSAR Section/Page C01 7.1.2.5/7.1-20 T1.8-1/2, 9,14, 27, 33, 41, 48, 51, 54 and 65 of 80 T7.1-1/4 and 5 of 6 C03 T1.8-1/42d of 80 8.3/8.3-70c C06 T1.8-1/48 of 80 C07 T1.8-1/2, 9, 14, 27, 33, 41, 48, 51, 54 and 65 of 80 T7.1-1/4 and 5 of 6 C22 7.5.5/7.5-15 C45 6.2.4.2/6.2-60 T6.2-60/9 of 10 E03 Q430.18/Q430.18-1 T430.18-1/1 and 2 of 2 E04 T1.8-1/63 of 80 8.3.3/8.3-82 E05 F6.2-122 F9.3-15 E08 8.3.2.1/8.3-74 E09 8.3.1.1.16/8.3-47, 48 and 49
e Attachnant #3 (Continued)
Action item FSAR Section/Page M01 3.98.2.2/3.9-6 3.98.3.1.2/3.9-9 3.9B.3.2.2/3.9-15 T3.9B-10/1 of 2 3.108.4/3.10-2 3.10N.1.2/3.10-4 3.10N.2/3.10-4 3.10N.4/3.10-5 M02 & M03 3A.1/3A-i,ii, 3A.1-2, l
2a,12 and 13 1
3A.2/3A.2-1, 2, 2a, 8, 10, 22, 22a, 22b, 22c, 22d and 22e F3A.2.1-5 F3A.2.2-2 P07 T6.2-57/1 of 1 S07 3.8.1.1.3.1/3.8-7 S12 3.8.3.3/3.8-34 3.8.4.5/3.8-46 and 47 EA Audit No. 50 T1.9-1/2 of 12 T1.9-2/12, 12a, 12b, 12c, 12d, 12e, 12f of 93 3.68.1.3.1/3.6-4