ML20235T097
| ML20235T097 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/07/1987 |
| From: | Grimsley D NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| To: | Airozo D MCGRAW-HILL PUBLICATIONS CO. |
| Shared Package | |
| ML20235T101 | List: |
| References | |
| FOIA-87-540 NUDOCS 8710090259 | |
| Download: ML20235T097 (4) | |
Text
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MSPONSE TYPE
'iESPONSE TO FREEDOM OF M **""*d N O S
N 00T 7 1987 l
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INFORMATION ACT (FOIA) REQUEST y
OOCKET NuMBERISI Uf appresomi
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i PART l.-RECORDS RELEASED OR NOT LOCATED (See checked boxesi No spency records subpct to the requent have been located.
No additonal agency records subsect to the request have been located.
A0ency records subset tn the requnst that are identified in Appendix are already eveamble for public inspection and copying in the NRC Public Document Room.
1717 H Street, N.W., Washmgton, DC.
Agency records subsect to the request that are identified in Appendix b
are being mMe evedaue for p@ic inspection and copying in the NRC Public Ducument Room,1717 H Street, N W., Washington, DC, in a folder under this FOIA number and requester name.
e The nonpropnetary version of the proposaHs) that you agreed to accept in a telephone conversation wrth a rnember of rny staff is now being made avaBable for public inopoetion Cnd coying et the NRC Public Document Room,1717 H Street, N W, Washington, DC, in a fo6 der under this FOIA ntrnber and requester name.
Enclosed is information on how you may obtam access to and the charges for copying records placed in the NRC Public Document Room,1717 H Street, N.W., Washington, DC Agency records aublect to the request are enclosed Any applicable charge for copies of the records prtmded and payment procedares are noted in the comments section.
Records subpet to the request have been referred to 3riother Federal agencyties) for review and direct response to you.
In view of NRC's response to the request, no further action is being taken on appeal letter dated 4
l PART li.A-INFORMATION WITHHELD FROM PUBUC DISCLOSURE Ccrtain informaton in the requessed records is being withheld from public disclosure pursuant to the FOIA esemptons described in and for the reasona stated in Part it, sec.
tions B, C, and O Any released portions of the documents for which only part of the record is being wrthheld are being made available for publec inspection and copyng in l
l the NRC Public Document Room.1717 H Street, N.W., Washington, DC in a folder under this FOIA nureer and requester name.
Comments l
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NMC FORM 464 iPen 11 Gael
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FREEDOM OF INFORMATION ACT RESPONSE FOIA NUMBERtSI:
PQQT tt 8-QPPLICABLE FOIA EXEMPTIONS Records subject to the request that are described in the enclosed Appendices are being withheld in ther er'trety or in paat under FOIA Esemptions and for the reasons set forth below pursuant to 5 U.S.C. 552(b) and 10 CFR 9.5(a) of NRC Regulations.
- 1. The withheld information a properly classifad pursuant to Executive Order 12356 (EXEMPTICN 1) 2 The wrthheld information relates solely to the internal personnet rules and procedures of NRC. (EXEMPTION 2) j j
3 The withheld information is specifically exempted from putec declosure by statute indicated. (EXEMPTION 3)
Section 141146 of the Atomic Energy Act which prohibets the desclosure of Restricted Data +or Formerly Restricted Data 142 U.S C. 214121fl5).
/
Section 147 of the Atomic Energy Act which prohituts the declosure of Unclass(ed Safeguards information (42 U S.C. 2167).
- 4. The withheid information is a trade secret or commercial or friencialinformation that is being withheld for the reason (s) indicated: tOIEWT10N 4)
The information is considered to be confidential business Ipropnetary) information.
The information is considered to be proprietary inforrnaten pursuant to 10 CFR 2.790(d)(1).
i I
The information was submitted and received in confidence from a foreign source pursuant to 10 CFR 2.790(d)(2L
- 5. The withhe6d information consists of interagency or intraagency records that are not available through discovery during litigation. D=*==e of predecisional information would tend to inhibit tho open and frank exchange of ideas eneontal to the deliberative process. Where records are withheld in their eneresy, the facts are inextricably intertwmed with the predecisenal informaten. There aino me no reasonably segregable factual portions because the reieces of the facss wasM permit an indrect inquiry into the predecissonal procese of the egency. (EXEMPTION N r
Q. The withheld information is exernpted from public disclosure because its dsclosure would result in a clearly unwarranted invasion of persortal privacy. (EXEMPTION 61
- 7. The withheld information consists of investigatory records compded for law enforcement purposes and is being withheld for the ressores) sidicated. (EXEMPTION 71 Declosure would interfere with an enforcement proceeding because it could reveel the scope, direction, and focus of enforcement ePortt and thus could poossbry allow them to take action to siseld potenhal wrongdceng or a violation of NT.C requirements from investigators. (EXEMPTION MA))
Dociosure would constitute an unwarranted invasion of personal pnvscy (EXEMPTION 7tC))
i The information consists of names of individuals and other information the disclosure of which woul(I reveal identrties of confidentas sources. (EXEMPTION 7tDH PART 11 C-DENYING OFFICIALS Pursuant to 10 CFR 9 9 and/or 9.15 of the U.S. Nuclear Regulatory Comrnmenson regulations, it has been determined that the information withheld is enerqpt from production or disclosure, and that its production or declosure is contrary to the putlic interest. The persons responsible for the denial are thoes offscais identified below as denying officists and the Director, DMason of Rules and Records Office of Administration, for any denses that may be opposted to the Executive Director for Operations EDOI DENylNG OFFICIAL TITLE / OFFICE RECORDS DENIED APPELLATE OFFICIAL hu HNLE W M Q{ 6U RE M R U {mWDN 9 X
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PART H D-APPEAL RIGHTS The denial by each denying official identified in Part ILC may be appealed to the Appellate Official identified in that section. Any such appeal must be in writing and must be made within 30 days of receipt of this response. Appeals must be addresand as appropriate to the Executive Dinoctor for Operations or to the Secretary of the Commission, U.S. Nuclear Reg'ula*ory Commission, Washington, DC 20566, and should clearly state on the envelope and in the letter that it is an " Appeal from an Initial FOIA Decision.
senc Ponta aos (Port a U.S. NUCLEAR REGULATORY CCMMISS(ON ossi FOIA RESPONSE CONTINUATION
Re: F01A-87-540 (SecondPartial)
APPENDIX C R.ECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER.
1.
3/4/87 Memorandum to George Felgate from E. William Brach, Background Information for Commissioner Carr's Visit to BeaverValley.(24 pag'es) 2.
7/10/84 Letter to Chairman Zech and Commissioners Bernthal and Carr from John M. Arthur, Beaver Valley. (1 page) 3.
8/14/87 Commissioner Carr's Notation Vote Response Sheet, 1
SECY-87-202. (1 page) l i
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Re: F01A-87-540 (SecondPartial)
APPENDIX D RECORDS TOTALLY WITHHELD - EXEMPTION (5) l 1.
Undated
. Chainnan's Vote Sheet on SECY-87-202. - (1 page) -
l 2.
Undated Commissioner Roberts' Vote Sheet on SECY-87-202. (1 page) 3.
8/11/87 Internal note from P. Gwynn to Chairman Zech re Vote on l
Beaver Valley Unit 2. (1 page) 4.
8/13/87 Commissioner Bernthal's Vote on SECY-87-202, subject:
Beaver Valley Power Station, Unit 2, Full-Power License.
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Auoust 17. 1987 Washington.
D.C.
Mr. Donnte Grimsley Director. Division of Rules & Records FREEDOW 0F INFORMATl0li U.S.
Nuclear Regulatory Commission Wasnsnoton.
D.C.
20555 ggyggggggy Fora 540 p
Deer Mr. Grimsleva Pursuant to the Freedom of Information Act. 5 USC 552 et seo.. as amended, or env other aoolicable laws. I herebv reouest th.e following material.
- 1) NRC Commissioners' notation vote sheet regardi.ng the full-power licensing 7
of Duouesne Licht Co.'s Beaver Valley-2.
- 2) All NRC staff or Duouesne L.ight Co. staff memoranda, notes, recommendations l
f or correspondence with NRC commissioners or their staffs. or other NRC l
o o r s o n n e'l concerning the low-oower testing and full-power operation of Beaver Vallov-2.
- 3) Information released under a FOIA filed by Office of Inseoctor & Auditor Director Sharon Conne11v NRC investigation concerning manner in which she and other OIA personnel handled an internal personnel matter (Lisa Shea. EEOC comolaint).
l If you have anv ouestions or recuire additional information. olease contact me et 463-1659.
Sincerely.
/
ave A roz Assistant Editor McGraw-Hill Nuclear Publications 1120 Vermont Ave.
Suite 1200 Washington, D.C.
20005 (202) 463-1659
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- o, UNITED STATES
,, '. i NUCLEAR REGULATORY COMMISSION 5' e o
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W ASHINGTON, D. C. 20555 MAR 4 1987 MEMORANDUM FOR:
George Felgate Assistant to Connissioner Carr FROM:
E. William Brach, Executive Coordinator i
for Regional Operations DEDROGR
SUBJECT:
BACKGROUND INFORMATION FOR COMMISSIONER CARR'S VISIT TO BEAVER VALLEY Enclosed is general background information on Beaver Valley Units 1 and 2 for your use in preparing for Commissioner Carr's visit to the site on March 10-11, 1987. The background papers include copies of the most recent SALP reports for both units (Unit 1 - operating, Unit 2 - construction) and a list of open SER issues for Unit 2.
If you need any additional information, please contact Bill Kane (Region I, FTS 488-1229) or me.
NY
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E. William Brach I
Executive Coordinator for Regional Operations DEDROGR Enclnsure: Background Information on Beaver Valley cc:
M. Clausen C. Ader J. Austin J. Meyer W. Kane, RI 4
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l BACKGROUND INFORMATION i
ON BEAVER VALLEY NUCLEAR POWER STATION Utility:
Duquesne Light Company Location:
Shippingport, Pennsylvania (5 mi E of East Liverpool, Ohio) 22 Mi'NW of Pittsburgh, Pennsylvania Beaver County, Pennsylvania Unit 1 Unit 2 Docket No.
50-334 50-412 CP Issued:
6/26/70 5/3/74 Operating Lic Issued:
7/2/76 Expected 8/87 Initial Criticality:
5/10/76 Elec. Ener.1st Gener:
6/14/76 Commercial Operation 10/1/76 Reactor Type:
PWR 3-loop.
Same Power Level:
835 MWe (DER): 2652 MWt (LTP) Same Architect / Engineer:
Stone & Webster Same NSSS Vendor:
Westinghouse Same Constructor:
Stone & Webster Same Turbine Supplier:
Westinghouse Same Condenser Cooling Method:
Natural Draft Cooling Tower Same Condenser Cooling Water:
Ohio River Same Licensing Project Manager:
Peter Tam, NRR (Tel: 492-4409)
NRC Responsible Region:
Region I, King of Prussia, Pennsylvania Thomas E. Murley, Regional Administrator l
Div. of Reactor Projects:
William F. Kane, Div. Dir (Tel: 8-488-1229)
(Region 1)
Edward C. Wenzinger, Branch Chief (Tel: 8-488-1224)
Iowell E. Tripp, Section Chief 3
(Tel: 8-488-1227)
David F. Limroth, Project Engineer (Tel: 8-488-1121)
Senior Resident Inspector (Unit 1): William M. Troskoski (Tel: 8-412-643-9200)
Senior Resident Inspector (Unit 2):
James E. Beall (Tel: 8-412-643-5274)
Resident Inspector (Unit 1):
Andra A. Asars (Tel: 8-412-643-9201)
Resident Inspector (Unit 2):
Leonard J. Prividy (Tel: 8-412-643-5320)
Report Coordinated by:
Andra A. Asars, Resident Inspector, Beaver Valley
- Fuel load date estimated to be 4/30/87.
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BEAVER VALLEY NUCLEAR POWER STATION Duquesne Licht - Site Management Personnel Jack Carey, Senior Vice President, Nuclear Group Jack Sieber, Vice President, Nuclear Group James Crockett, Senior Manager, Nuclear Operations l'
Unit 1 Steve Lacey, Plant Manager Gene Ewing, Manager, Quality Assurance Unit 2 Jack Kline, Manager, Engineering and Construction Rich Swiderski, Project Manager Gene Ewing, Manager, Quality Assurance Workforce Staffing level at the plant:
Unit 1 = 600, plus corporato personnel also located on site.
Unit 2 = 5900 Workshifts Unit 1 - Five rotating shifts (3 working shifts,1 off-shift and 1 training).
Unit 2 - Three working shifts with 4000 on daylight shift, 1200 on evening shift and 700 on night shift.
On weekends, there l
are two shifts, daylight and evening with approximately l
900 and 200, respectively.
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Personnel on Each Shift Unit 1 (Operations):
2 Senior Reactor Operators (SR0s) 2 Reactor Operators (R0s) 1 Shift Technical Advisor 1
2 Auxiliary Operators Licensed Reactor Operators Total Licensed Reactor Operators:
61 (Unit 1) 23 Sk0s (which includes 17 in plant management) 38 R0s 1
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BEAVER VALLEY NUCLEAR POWER STATION Reactor Operator Exams i
Unit 1 Date Of Number Of 4
Exam-Applicants Passed Failed i
10/84 12 SR0s 11 SR0s 1 SR0 3 R0s 2 R0s 1 R0 2/85 6 R0s 3 R0s 3 R0s 4/85 11 R0s 11 R0s 2/86 11 SR0s 4 SR0s 7 SR0s 5 R0s 5 R0s 7/86 5 SR0s 3 SR0s 2 SR0s 12 R0s 7 R0s 5 R0s Unit 2 1/87 12 SR0s (Results not yet available) 8 R0s Next Exam Scheduled:
5/87 (Expected to have 12 SR0s and 7 R0s).
Plant Simulator A Unit 1 plant-specific simulator is located onsite in the training center.
The simulator was made operational in March 1985.
Control Room Currently, there is a temporary wall separating the Unit I and Unit 2 control rooms. The licensee plans to remove this wall in March-April 1987.
Systematic Assessment of Licensee Performance (SALP)
EhviewJwas congleted for the period' April 1,1984'throMM Milla
. r 30, 1985, and a report issued on May 23, 1986. A copy of this Septe report is attached (Attachment 1).
The next SALP review period for Unit 1 covers October 1, 1985 through March 15, 1987.
The Region I SALP board is scheduled to meet the week of May 4, 1987.
A SALP report is expected to be issued approximately May 29, 1987.
A meeting with the licensee is scheduled i
i-for early June 1987.
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AUnit2SALPreviewwascompletedfortheperiodApril1,1985throughlMarch I
31, 19867;This report was issued on July 2, 1986; a copy is also attached j
(Attachment 2). The next SALP review period for Unit 2 covers April 1, 1986.
through February 28, 1987.
The Region I SALP board is scheduled to meet the week of April 20, 1987. A SALP report is expected to be issued approximately May 10, 1987.
A meeting with the licensee is scheduled for mid-May 1987.
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BEAVER VALLEY NUCLEAR POWER STATION i
The current Beaver Valley Unit 2 SALP is likely to assess the licensee's per-formance as generally satisfactory (or higher).
The licensee has shown im-1 provement in the areas of implementation of design changes and managing and meeting test ailestone dates.
The licensee has been particularly effective in coordinating schedule adjustments during major preoperational tests.
How-ever, continued management attention will be necessary to ensure that the-Quality Assurance Program is implemented effectively.
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Escalated Enforcement Action The Unit I resident inspectors received an allegation on May 27, 1986, from 1
a contractor radiation technician as he was escorted offsite after having his employment terminated.
The alleger expressed several concerns in the areas of radiation control practices and industrial safety.
These allegations were investigated by a Region I Health Physics specialist during a subsequent in-spection; the allegations were not substantiated and no violations were iden-l tified.
The alleger filed a complaint with the Department of Iabor claiming unfair job termination.
A DOL field investigation determined that he was wrongfully fired by the utility and its subcontractor.
The licensee has set-1 tied this matter out of court.
As a result of this allegation, and in accord-ance with 10 CFR 50.54(f), Region I requested that the licensee provide as-surance that this matter has not had a " chilling" effect in discouraging con-tractor or DLC personnel from bringing safety concerns to NRC's attention.
Thelicensee'sresponseiscgrrentlybeingevaluated.
In September 1986, an inspector identified a violation of NRC reporting re-quirements at Unit 2.
In 1983 and 1984, DLC and Stone & Webster Engineering had identified deficiencies with some Westinghouse 7300 Process Protection System circuit cards.
However, the inspector determined that the Construction Deficiency Report filed in accordance with 10 CFR 50.55(e) did not contain an adequate description of corrective actions and was not reported in a timely manner.
This violation is currently under consideration for escalated en-forcement action.
3 Emergency Preparedness An emergency preparedness exercise for Unit I was conducted successfully in November 1986.
The licensee has been rated as Category I in emergency pre-i paredness in the past several SALPs.
l A Unit 2 emergency preparedness exercise is scheduled for October 1987.
Emergency Response Facilities (ERF)
I The Emergency Operations Facility (EOF), Technical Support Center (TSC), and Operational Support Center (OSC) became operational in the summer of 1985.
The licensee's actions with respect to Supplement 1 to NUREG-0737 cannot be
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closed until an Emergency Response Appraisal is conducted by the NRC.
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r BEAVER VALLEY NUCLEAR POWER STATION Plant Status - Unit 1 Unit 1 was shutdown for a refueling outage May 16, 1986 through August 8, 1986.
The next refueling outage is scheduled for November 1987.
Unit 1 is operating at 100% licensed rated power.
Cumulative capacity factor is low, approximately 50.4%.
This is primarily due to a 12-month major, shutdown imposed by the Commission to backfit seismic requirements.
Refueling outages also tend to be long due to numerous modifi-cations.
More recently the yearly capacity far,',or has been on par with other reactors; e.g., 67.3% for 1986, 83.2% for 198b, 66% for 1984, and 66% for 1983.
s plant Status - Unit 2 Applicant's percent construction completed:
98.7% as of January 1987.
Current work activities include: completion of preoperational testing includ-ing the loss of offsite power tests, and installation of cable wraps and tray covers.
I An as-built team inspection is scheduled for the weeks of March 16 and 23, 1987.
A Technical Specification verification team inspection is scheduled for the weeks of March 30 and April 6, 1987.
These teams will review as-built safety-related systems, structures and components to verify compatibility with the Unit 2 Technical Specifications, FSAR, and supporting safety analyses.
The SER was issued October 1985 (3 supplements have been issued, 2 more are expected).
Fuel load is scheduled for April 30, 1987.
Significant Open Issues in the SER There are no significant open issues in the SER.
However, the list of open issues and confirmatory issues are attached.
(Attachement 3).
All open issues can be closed prior to licensing.
Attachments:
1.
Unit 1 SALP report dated May 23, 1986.
2.
Unit 2 SALP report dated July 2, 1986.
3.
SER Open Issues and Confirmatory Issues 4.
Site Location and Area Maps f
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- v BEAVER VALLEY NUCLEAR POWER STATION Location and Description The Beaver Valley Power Station is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River.
The site is ap-proximately one mile from Hidland, Pennsylvania, five miles from East Liver-pool, Ohio, and approximately 25 miles from Pittsburgh, Penr.sylvania.
The site comprises approximately 501 acres. -Al or The SAPS terminated operations October 1, 1982.
Local site topography, site boundary and exclusion radii are shown in Figure 1.0.
Phillis Island lies approximately 400 feet off the shoreline of the site.
This island is being excavated as a borrow source for aggregate.
Population The distance and direction to population centers that have more than approxi-mately 25,000 inhabitants and are located within 50 miles of the site and listed in Table 1.0.
The location of these population centers is shown in Figure 2.0.
1 The approximate distribution of the 1985 population based on census reports, topographic maps, aerial photographs, and field observation is shown in Figure j
3.0 when combined with Table 2.0 for 16 directional sectors and radial dis-tances in on-half mile increments out to a distance of 10 miles from the sta-tion.
Incremental and cumulative populations at these distances are listed in Table 2.0.
Major public facilities in the vicinity of the site are presented in Table i
3.0.
Industry The general area in which the site is located is part of the large Pittsburgh industrial complex, which is centered about the City of Pittsburgh.
Table 4.0 lists the major employers in the area surrounding the site.
Transportation The region is served by five transportation systems; railroads, highways, air, pipelines and waterways.
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W One of the first rail lines in the region ran from Pittsburgh up the eastern bank of the Beaver River to the Great Lakes region.
That line is one of the main Penn Central lines.
The world's largest electrically controlled railroad switching yards, capable of handling 10,000 cars per day, is located on this line at Conway about ten miles east of the site.
State Highway 68 provides the main access from the residential areas east of
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the site to the industrial complexes along the north bank of the Ohio River.
State Highway 168 from the south follows roughly along the northeast and east corner of the site _and, crossing the Shippingport Bridge,. joins Highway 68 immediately across the river from the site.
State Highway 18 pr>vides addi-tional access to the east of the site which U.S. Route 30 passes by three miles southwest of the site.
The nearest interstate highway to the site is the Pennsylvania Turnpike (I-76) which runs through the northeastern section of Beaver County about 15 miles j
northeast of the site.
Interstate 79 is located about 18 miles east of the 1
site while Interstate 70 which goes through Wheeling, West Virginia, is about j
30 miles to the south.
Figure 4.0 shows the local area highway map.
The most important airport in the region for passenger and freight service is the Greater Pittsburgh International Airport, located about 15 miles south-east of the site.
The areas is also served by pipelines carrying natural gas and petroleum pro-ducts. There are six pipelines crossing the site.
The Ohio River is a major natural resource in this region.
In addition to supplying water to industry and towns in the valley and transportation for bulk freight in and out of the region, it serves as a source of recreation for fishermen and boaters alike.
Attachments:
Figure 1.0 (Local Site Topography) i Figure 2.0 (Counties and Towns within 50 Miles)
)
Figure 3.0 (Population - Distribution)
Figure 4.0 (Site Location)
Table 1.0 (Population Centers with over 25,000 People)
Table 2.0 (Population Distribution for 1985)
Table 3.0 (Public Facilities)
Table 4.0 (MajorEmployers)
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kJ Table 1.2 Open issues
. Issue Status SER section L
(1) Preservice/ inservice testing program i.
(a) PST Deleted in SSER 3 3.9.6 l
(b) IST Under review 3.9.6 i
(2) Pump and valve leak testing Closed in SSER 3-3.9.6 (3) Inadequate core cooling instruments-Closed in SSER 2 4.4.7 tion (Item II.F.2 of NUREG-0737)
(4) Preservice/ inservice inspection program Under. review 5.2.4.3, (a) PSI
'5.4.2.2, (b) ISI Updated in SSER 1, 6.6 l
remains open
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(5) Safe and alternate shutdown Unchanged from SER 9.5.1 (6) Management and organization Under review 13.1 (7) Cross-training program Closed in SSER 1 13.2.1.2 (8) Emergency preparedness plan Under review 13.3.3 (9) Initial test program Closed in SSER 3 14 (10) Control room design review Updated in SSER 1, 18.1 remains open I
(11) Safety parameter display system Updated in SSER 1, 18.2 remains open Beaver _ Valley 2 SSER 3 1-2
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e Table 1.3 Backfit issues Status
- SER section issue C
2.3.1 (1) Snow and ice load (2) Underestimation of atmospheric dispersion C
2.3.4, 15.4.8 conditions (X/Q) at exclusion area boundary j
and consequences of radioactive release (3) Potential for flooding from probable maximum C
2.4.2, 2.4.10 precipitation and Peggs Run (4) Steam generator level control and protection C2 7.3.3.12 C
8.3.1.12 (5) Motor-operated accumulator isolation valve C
9.1. 3 (6) Spent fuel pool maximum heat load A
9.5.1.6 (7) Fire suppression in the cable spreading room (8) Class 1E power for lighting and communication C
9.5.2.1 systems C
9.5.2.1 (9) Application of GDC 5 to communication systems C
9.5.2 (10) Application of GDC 2 and 4 to communication systems C
9.5.3 (11) Application of GDC 4 to lighting systems (12) Illumination levels in excess of SRP criteria C
9.5.3 C
9.5.4-9.5.8 (13) Application of RG 1.26 to areas excluded by RG 1.26 C
9.5.6 (14) Air dryers for emergency diesel generator C
9.5.7 (15) Alarm for rocker arm lube oil reserve C
9.5.7 l
(16) Diesel lube oil fill procedure
- A - Issue was discussed in appeal meeting, and partial resolution was ad-dressed in the SER (October 1985).
Status updated in SSER 3.
C - Closed in SER (October 1985).
C2 - Closed in SSER 2, confirmatory issue 49 opened.
l Beaver Valley 2 SSER 3 1-3
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n Table 1.4 Confirmatory issues Issue Status SER section (1) Operating procedures for continuous Closed in SSER 3 2.2.2 communication links I
(2) Differential settlements of buried pipes Under review 2.5.4.5 (3) Internally generated missiles (outside Unchanged from SER 3.5.1.1 containment)
(4) Internally generated missiles (inside Unchanged from SER 3.5.1.2 containment)
(5) Turbine missiles Unchanged from SER 3.5.1.3 (6) Analysis of pipe-break protection Unchanged from SER 3.6.1 outside containment (7) FSAR drawings of break locations Unchanged from SER 3.6.2 (8) Results of jet impingement effects Unchanged from SER 3.6.2 (9) Soil-structure interaction analysis Closed in SSER 1 3.7.3 (10) Design documentation of ASME Code Closed in SSER 2 3.9.3.1 components I
(11) Item II.D.1 of NUREG-0737, pressure /
Under review 3.9.3.2 relief valves (12) Seismic and dynamic qualification of Under review 3.10.1 mechanical and electrical equipment (SQRT) l (13) Pump and valve operability assurance Under review 3.10.2 (PVORT) l (14) Environmental qualification of Under. review 3.11 mechanical and electrical equipment (EQRT)
(15) Peak pellet design basis Closed in SSER 1 4.2.1 (16) Discrepancies in the FSAR Closed in SSER 1 4.2.2 (17) Rod bowing analysis Closed in SSER 1 4.2.3.1(6) i (18) Fuel rod internal pressure Closed in SSER 1 4.2.3.1(8)
(19) Predicted cladding collapse time Closed in SSER 1 4.2.3.2(2)
Beaver Valley 2 SSER 3 1-4 1
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Table 1.4 (Continued)
Issue Status SER section
)
(20) Use of the square-root-of-the-sum-of-Closed in SSER 1 4.2.3.3(4) the-squares method for seismic and
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loss-of-coolant-accident load I
calculation (21) Analysis of combined loss-of-coolant-Under review 4.2.3.3(4) accident and seismic loads (HULTIFLEX)
(22) Natural circulation test Updated in SSER 1; 5.4.7.5 remains open
)
1 (23) Reactor coolant system high point vents Closed in SSER 3 5.4.12
(.M) Blowdown mass and energy release Under review 6.2.1.3 analysis methodology 1
(25) Containment sump $0% blockage assumption Updated in SSER 2; 6.2.2 remains open (26) Design modification of automatic reactor Under review 7.2.2.3
)
trip using shunt coil trip attachment j
i (27) Automatic opening of service water Closed in SSER 1 7.3.3.10
{
system valves MOV113C and 113D l
(28) IE Bulletin 80-06 concerns Unchanged from SER 7.3.3.13 (29) NUREG-0737, Item II.F.1, accident Closed in SSER 1 7.5.2.2 monitoring instrumentation positions (30) Bypass and inoperative status panel Under review 7.5.2.4.
(31) Revision of the FSAR--cold leg accumu-Closed in SSER 3 7.6.2.4 lator motor-operated valve position indication (32) Control system failure caused by Under review 7.7.2.3 malfunctions c.f common power source or instrument line (33) Confirmatory site visit (a) Independence of offsite power Closed in SSER 1 8.2.2.3 between the switchyard and Class 1E system (b) Confirmation of the protective Closed in SSER 1 8.3.1.2 bypass Beaver Valley 2 SSER 3 1-5 j
t c
- v Table 1.4 (Continued) i Issue Status SER section (33) Confirmatory site visit (Continued)
(c) Verification of DG start and load Closed in SSER 1 8.3.1.8 bypass (d) DG load capability qualification Closed in SSER 1 8.3.1.9 test (e) Margin qualification test Closed in SSER 1 8.3.1.10 (f) Electrical interconnection between Closed in SSER 1 8.3.1.13 1
I redundant Class IE buses (g) Verification of electrical Closed in SSER 1 8.3.3.5 1
independence between power supplies l
to controls in control room and remote locations l
(34) Voltage analysis--verification of test Unchanged from SER 8.3.1.1 results (35) Documentation of des:ription and analysis Unchanged from SER 8.3.3.7.1 of compliance with GDC 50 (36) Completion of plant-specific core damage Unchanged from SER 9.3.2.2 estimate procedure before fuel load (37) Training program for the operation and Unchanged from SER 9.5.4.1 maintenance of the diesel generators (38) Vibration of instruments and controls on Unchanged from SER 9.5.4.1 diesel generator (39) Surveillance of lube oil level in the Closed in SSER 2 9.5.7 diesel generator rocker arm lube oil reservoir (40) Solid waste process control program Unchanged from SER 11.4.2 (41) TM1 Action Plan items (a)
III.D.1.1, postaccident reactor Under review 13.5.2 coolant leakage outside containment (b)
II.K.1.5 and II.K.1.10, IE Bulletins Under review 15.9.2, on measures to mitigate small-bre n 15.9.3 LOCAs and loss of feedwater (c)
II.K.3.5, automatic reactor Under review 15.9.9 coolant pump trip during LOCA Beaver Valley 2 SSER 3 1-6 I
' i '
- ?'*
c o
Table 1.4 (Continued)
Status SER section Issue (41)'TMI Action Plan items (Continued)
(d)
II.K.3.17, report on ECCS outage Under review 15.9.11 (e)
II.K.3.31, compliance with Closed in SSER 3 15.9.14 10 CFR 50.46 Closed in SSER 2 15.4.2 (42) Plant-specific dropped rod analysis Under review 15.6.3 (43) Steam generator tube rupture Closed in SSER 1 17.4 (44) Quality assurance program Under review 13.2.1.1 (45) Cross-training of Unit 1 & 2 operators (46) Control room isolation on high radiation.
'Under review 7.3.3.9 1
signal (47) Review of procedures generation package Unchanged from 13.5.2 SSER 1 (48) Fire protection:
Amendment 12 review and site visit (a) Amendment 12 review Closed in SSER 3 9.5.1 (b) Site visit Unchanged from 9.5.1 SSER 2 (c) Safety-related system Opened in SSER 3 9.5.1 fire-barrier deviations (49) Steam generator high-level trip as non-Unchanged from 7.3, SSER 2 15.1.2 protection system (50) Implementation letter of ICCI system Unchanged from 4.4.7 SSER 2 (51) Supperheated steam in valve house Opened in SSER 3; 3.6.1 under review due to steamline break (52) Initial testing (a) Accumulator isolation valves Opened in SSER 3 14.0 (b) 50V, P0, IS tests Opened in SSER 3 14.0 Beaver Valley 2 SSER 3 1-7
i^
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=
_ c...._
q l
+
.6 Table 1.4 (Continued)
Issue Status SER section I
(52) Initial testing (Continued)
(c) Plant performance after MSIV Opened in SSER 3 14.0 l
closure (d) Steam extraction system and Opened in SSER 3 14.0
-process computer I
Table 1.5 License condition issues License condition Status SER'section-(1) Emergency response capability,
. Specifics provided 7.5.2.1~
RG 1.97, Rev. 2 in SSER 1;.under' 4
additional generic review-(2) Fire protection Opened in SSER 3 9.5.1 i
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- A BVPS-2 FSAR i
TABLE 10 ) POPULATION CENTERS WITH OVER 25,000 PEOPLE IN 1980 l WITHIN 50 MILES OF BVPS-2 l { Distance
- and 1
Direction 1980 l City / Township / Borough County from Site Population I i Pennsylvania ** New Castle City Lawrence 23.5 miles /N 33,621 1 f Bethel Park Borough Allegheny 28 miles /SE 34,755 I McCandless Township Allegheny 17 miles /E 26,25G j f McKeesport City Allegheny 35 miles /ESE 31,012 Monroeville Borough Allegheny 36 miles /ESE 30,977 Mt. Lebanon Borough Allegheny 26 miles /SE 34,414 Penn Hills Township Allegheny 31 miles /ESE 57,632 Pittsburgh City Allegheny 22 miles /ESE & SE 423,938 Plum Borough Allegheny 32 miles /ESE 25,390 Ross Township Alclegheny 21 miles /ESE 35,102 ) Shaler Township Allegheny 24 miles /ESE 33,694 West Mifflin Borough Allegheny 32 miles /SE 26,279 Hempfield Township Westmoreland 45 miles /ESE 43,396 i North Huntingdon Westmoreland 39 miles /ESE 31,517 i Township l l Ohio *** Warren City Trumbull 45 miles /NNW 56,629 Canton City Stark 50 miles /WNW 110,053 Plain Township Stark 48.5 miles /WNW 32,431 Steubenville City Jefferson 23 miles /SSW 26,400 Austintown Township Mahoning 34 miles /NNW 37,664 Boardman Township Mahoning 33 miles /NNW 41,833 I Youngstown City Mahoning 32 miles /NNW 115,427 f West Virginia **** Wheeling City Chio 36.5 miles /SSW 42,874 NOTES:
- Distance to closest boundary
- U.S. Department of Commerce, Bureau of the Census, 1982a.
- U.S. Department of Commerce, Bureau of the Census, 1982b.
- U.S. Department of Commerce, Bureau of the census, 1982c.
- U.S. Department of Commerce, Bureau of the Census, 1982b.
- U.S. Department of Commerce, Bureau of the Census, 1982a.
7137 8205 9658 2109 2485 5690 2760 5497 6 l 1 5,3,7, 4,5 1 5, 1 4,5,8, 3,4,6,1, 1 t 3816 7021 2122 6762 3 a o 21 21 2 4 1 T D 9126 1206 4244 2035 1 6529 5669 3049 7846 5
- 5. L 9 8,8,2, 4663 4465 4,2,2 2 3,
8I 62 2 320 47 6 11 1 5570 7174 5571 0952 0 3048 6216 2050 2107 4 0.M579,0, 4,262 5,3,3 3 3, 5437 7 42 01 23 9 1 - 3 1 4932 0881 5458 1053 6 8966 9987 4245 0880 9
- 6M2555, 2,3 0
26 8,3 1, 1 4 4 13 1 1 2036 6530 9268 0908 9 7210 3658 7584 0499 4 0.J 46,53 3,536 5, 2331 4225 56 2 0 S 2 1 E L I 0224 3906 2703 3687 2 M 3334 46 4 8797 9234 2 5.M212 1 3 1 413 6, 0 4 2 1 ) 0 s l 8133 0409 9785 5256 5 e 5 i 5083 04 6 3452 2621 8 5, 0.M11 11 1 1 13 8 m 4 1 9 ( 1 2 R O S 8249 7559 3965 4090 5 0 3722 8736 183 2 F P 5.M3696 1 11 1 24 8, 2 V N B 3 1 E O m L I B T o A U r 0212 5241 2851 4307 7 7286 2606 5236 2 0.M2869 T B 'f 2 5 21 2 2 2, I R e 3 2 T c S n O t 7150 3810 9888 660^ 0 I a s R 4450 0732 6270 3 85 5 N i
- 5. L 31 1
1 21 6, 1 2 O D 1 3 I T AL 7752 9369 6004 2096 5 6564 2595 2 52 4 2M 3256 0 U 1 2 1 5 6, P O 1 P 7400 1747 4227 1184 9 5.M31 433 127 1146 1 9 8, 3 11 1 1 O705 6391 1144 4016 2 5 1 11 11 69 0 0.M 0, 3, 1 1 1 . O575 1 O046 0922 0100 5.M 35 2 1 87 0 2 5 0 Oo42 861O 0D0D O0D0 1 0.M 7 2 2 1 0 n o i t c l a e r E E E E W W W W t MEN SES SWS sWN o f i D NNNE EESS SSSW WWNN T
i O 6 TABLE 3.0 PARKS AND RECREATION FACILITIES WITHIN 10 MILES OF BVPS-2 Approximate Distance 1981 from Direction Attendance Station from Park / Recreation Area Sponsorship (visitor-days) (Miles) Station Game Lands Pennsylvania Not 7 SSE Number 189 Game tabulated (18 Commission Game Lands Pennsylvania Not 3.5 NNW Number 173 Game tabulated (18 Commission Raccoon State Park State of 468,852<2: 6 9(3) s.sswis) Pennsylvania Brady Run County Beaver 32,300(4) 8-9(58 NNW f Park
- County, Pennsylvania Tomlinson State State of 193,880465 10 SW-WSW(7)
Park West Virginia Beaver Creek State of Ohio 729,930ss> 10 WNW State Forest !!OTES: I
- 1. Pennsylvania Department of Natural Resources, Game Commission 1982a.
- 2. Pennsylvania Department of Natural Resources, Bureau of State Parks 1982b.
- 3. Allocates visitors to south sector, 8 miles from station at park entrance and camping areas.
- 4. Besver Valley Parks Department 1982.
- 5. West Virginia Department of Natural Resources 1982.
- 6. Operates May 21-September 30, allocates visitors a miles from station at park entrance.
- 7. Allocates visitors equally between SW and WSW sectors.
- 8. Ohio Department of Natural Resources, Division of Parks and Recreation 1982.
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