ML20198C572
| ML20198C572 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/31/1997 |
| From: | Cotton J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20198C576 | List: |
| References | |
| NUDOCS 9801070346 | |
| Download: ML20198C572 (10) | |
Text
-
. John B. Cotton Vr.a PresrJent sm.cn sacri A
=iEF" 10CFR50.54(a)(3)
PECO NUCLEAR no m vc - v 965 Chesterbrook Blvd A Unit of PECO Energy gvgggoB7-5691 r
a December 31,1997 Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
Limerick Generating Station, Units 1 and 2 Submittal of Revision 7 of the Updated Final Safety Analysis Report
Dear Sirs:
In accordar.ce with 10CFR50.71(e)(4) and 10CFR50.4(b)(6), this letter submits one (1) original and ten (10) copies of Revision 7 of 15e Updated Final Safety Analysis Report (UFSAR) for Limerick Generating Station (LGS), Udts 1 and 2. The enclosed copies of Revision 7 are being provided to the NRC on a replacement page basis with a list of effective pages identifying the latest revision date of all current pages in accordance with 10CFR50.71(c)(1). In each revision package, we have also provided page replacement instructions for incorporating Revision 7 page changes into the LGS UFSAR. As required by 10CFR50.71(e)(5), each replacement page includes a vertical line in the margin adjacent to each area changed, and the date of change is included on each page. Revision 7 reflects changes made up to a maximum of six months prior to this submittal in accordance with the requirements of 10CFR50.71(e)(4). As a result, the UFSAR Revision 7 package, has been made to reflect changes made to LGS, Units 1 and 2, under the provisions of 10CFR50.59, at least up to June 30,1997.
The encioeed UFSAR Revision 7 also contains the annual revision of the Quality Assurance Program Description (QAPD) which is being submitted in accordance with 10CFR50.54(a)(3).
The updated QAPD 0.e., Section 17.2 of the UFSAR Revision 7) reflects editorial and organizational charges. Attachment 1 provides a listing of those changes which have been made since the previous submittal in accordance with 10CFR50.54(a)(3)(ll). Based on the information provided in Attachment 1, we have concluded that the QAPD changes included in Revision 7 of the UFSAR do not reduce the commitments in the QAPD previously accepted by 1
the NRC.
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-9901070346 971231 A.
PDR ADOCK 05000352 K
PDR I.lll.llil.ll.1.Il. II!.!
December 31,1997 Page 2
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As required by 10CFR50,71(e)(2)(1), l certify that to the best of my knowledge, Revision 7 of the UFSAR accurately reflects information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above. In addition, as required by 10CFR50.71(e)(2)(ll), to this letter identifies changes made under the provisions of 10CFR50.59, and included in the enclosed Revision 7, but not previously submitted to the NRC.
If you have any questions or require further information, please contact us.
Very truly yours,
& Jh Enclosure Attachments cc:
H.'J. Miller, Administrator, Region I, USNRC (w/ attachments and enclosure)
A. L Burritt, USNRC Senior Resident inspector, LGS (w/ attachments and enclosure)
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ATTACHMENT 1l Page1 d 3 PECO Nuclear
- Qualty Assurance Program Description Changes 8.GU UFSAR, Revision 07
+
' item - _ Paragraph Change-
' A - Numbar Description d Change Classification 1.-
17.1' Deleted *Oualty Assurance during Design Editorial and Construction' from the Table d Contents because the phase is comploie and not '
addressed in the body d the OAPD.
2.
17.2 Deleted sentence regarding radioactive Editorial material packages. Overall QA Program applicability is addressed in 17.2.2.8.
1 3.
17.2.1.2 and -
Added wording and a paragraph to address Organizational 17.2.1.2.3 the new Nuclear Planning and Development and Edhorial.
Department; Renumbered previous paragraphs 17.2.1.2.3, 4, and 5 inclusive to 17.2.1.2.4 through 17.2.1.2.6.12.
- 4. _
17.2.1.2.4.a Added the words ' meteorological Clarification monitoring" for cla Ity and consistency with the Peach Bottom QAPD.
i S.
17.2 Minor wording changes Edkorial and 17.2.1 Organizational 17.2.1.2 17.2.1.2.4 17.2.1.2.4.1 17.2.1.2.4.1.1 17.2.1.2.4.1.2 17.2.2.2
-17.2.2.3 17.2.9.7
- 6. :
17.2.1.2.4.1.1 Deleted the words ' Technical Specifications
- Clarification (TS) because discussion of assessments
- performed under the Nuclear Review Board (NRB) has been moved from the TS to the QAPD.
.17, 17.2.1.2.4.3 and '
. Combined both sections into one because the Edkorial and 17.2.1.2.4.3.1 Manager, Corporate Nuclear Qualty (CNO) is Organizational responsible for both.' The change eliminates redundancy that resulted from listing responsibilkies twice. Also, included reference to the Nuclear Planning and Development Department.
4 ATTACHMENT 1 Page 2 of 3 PECO Nuclear QualRy Assurance Program Description Changes LGS UFSAR, Revision 07 Item Paragraph' Change
- Rct Number Description of Change Classification s
8.
'17.2.1.2.6.5 Changes made to NRB composkion to reflect ' Organizational
-17.2.1.2.6.9.1 recent reorganization and maintain a constant ECR 97 02006 17.2.1.2.6.10 number of NRB members. The Director of -
17.2.1.2.6.11 Nuclear Engineering DMalon (NED) was changed to an attemate member to the Vice Preskient (VP) of the Station Support Department (SSD). Additional changes were made for consistency with the PB OAPD, 9.
17.2.1.4.1 Deleted " Claims' from description of Organizational Security DMalon.
10.
17.2.2.4 Deleted wording related to Plant Operation Clarification Review Committee (PORC) review and approval of Surveillance Test proceduras. The Technical Specifications, revised per-Amendment No. 47 to reflect the Site Qualified Reviewer Process (SOR), address the procedure review and approval process under sections 6.5.1.6, 6.1.5.7. 6.5.3, and 6.8.1.
11.
17.2.3.3 Providea clarification to previous wording by Clarification replacing the second sentence. The electronic Plant Information Management System (PIMS) is used to control design documents such as Engineering Change Requests (ECR). PIMS provides for Indicating the status levels for design documents and their ce,*. ability for use.
12.
17.2.5.2 Replaced _words " Job Tickets
- with " Work Clarification Order" to reflect current process and terminology.
?
13.
17.2.10.1 Replaced the words *Such persons' in the Clarification third sentence with *OV personnel
- to clarify that OV personnel are responsible for
- Inspection, and are independent from those responsible for the work being inspected.
5 ATTACHMENT 1
. Page 3 of 3 L PECO Nuclear
=
-- item 1 : Paragraph Change K. Numhar Dancription of Ch'4)ge ClanalRcation i
' 14l 17.2.10.4.2 Deleted the words 1or which Nuclear ClarWication Ergic z;,g is responsible" an inspection is required fe' au modiRcations in accordance
. ith eetablished procedures.
w i
15; 17.2.12.4.
Replaced Station Support with Nuclear Organizational Planning and Development to reRect organizational change t
16.
' 17.2.18.6h and Combined two sub paragraphs relating to the ClarWication 17.2.18.6.1 Radiological Environmental Monitoring Program (REMP) assessment, into one by -
deleting 17.2.18.6.1. The consolidation eliminates redundancy and achieves consistency with the PB OAPD.
17.
Figure 17.21 Updated Corp ste Leadership Chart Organizational Irp 18.
Figure 17.2-2 Updated PECO Nuclear Organization Chart Organizationsi i
19.
Appendix 17.2.ll, Revised previous commitment to Regulatorv Programmatic item g.
Guide 1,54 - Protective Coatings - with -
ECR 97-04127 commitment to ASTM D 3843-93.
20.
Appendix 17.2.11, Added paragraph 5. to permit the flexibility to Programmatic item p.
conduct onW vendor evaluatAns in-place ECR 97-00406 of annual vendor evaluation process. The amendment was approved by the NRC as documented in letter cated June 26,- 1997, 2'
Appendix 17.2.ll, Added altomative to allow qualWication of Programmatic item q.
Lead Assessors on the basis of one
- ECR 97-00500
-assessment when approved by the Director-
-~
NOA.- The amendment was approved by the NRC as documented in letter dated June 26, 1907.
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ATTACHMENT 2 Page1 d 3 10CFR50.71(e)(2)(li) requires that revisions to tho UFSAR include changes made under the provisions of 10CFR50.59, but not previously submitted to the NRC. Accordingly, the list below identifies those plant modifications and projects included in Revision 07 of the Limerick Generating Station, Units 1 and 2 Updated Final Sa'ety Analysis Report (UFSAR). The list.dgesact represent a complete list of UFSAR-change pack &ges incorporated into Revision 07.
ModWicailon Unit
- Number Number Descriotion P00165 1&2 Modification of the LGS MCR Computer Consoles and Replacement of the Unit 2 PMS Toshiba Hardware.
P00326 1&2-Plant Heating Steam Coll Condensate Drain Modification.
P00391 1&2 Hydrogea Water Chemistry Permanent installation.
P00411 2
Install Precoatless Filter Elements & Modify Existing Backwash System to Air Surge System on the Cond F/D.
P00458 2
Electrohydraulic Control Reliability Enhancements.
P00512 1&2 Modification of the Reactor Enclosure Crane.
95-00078 P00565 2
Unit 2 Drywell 480/120V Outage Power.
96 41017 P00573 2
HV-C-44-CF033 Leaks by Pressurizing 95-02024 Downstream Piping.
P00580 2
Turbine Rotor Retrofit - Cycle Isolation Valve.
P00604 1&2 Snubber Replacement.
9641384 P00610 1&2 Installation of Work Management Centers 9545377 Outside Turbine / Reactor Buildings.
P00649 1&2 Main Control Room HVAC Habitability 96-01754 Improvements.
P00674 2
Replacement of the 2A RHR Pump Motor 2A 96-01019 P202-DR.
x ATTACHMENT 2 Page 2 of 3 -
Modification Unit Number Number Descriotion
. 95 45209 1
- Battery Cables for DMalon 3 and DMalon 4 Safeguard Battery Cart.
9640719 2
Perform Pressure Locking Mod on HPCI
- Injection Valve.
96-00720 2-Perform Pressure Locking Mod on HPCI Injection Valve.-
96 40721 2
Perform Thermal Binding Mod on RCIC injection Valve.
96-01084 2
Design Permanent Jumper Connections for 2A(B)-C248.
9641192 2
Modify Valve for Pressure Locking.
9641469 2
Construct and insts.108 Levil Sightglass on RCIC Turbines.
9641472 1&2 08-K114 MCR Chiller Pumpout Compressor Rework 9641515 1&2 Replace 'A' MOR Chiller Pumpout Piping.
9641594 2
Modify Valve for Pressure Locking.
I 96-01597 2
Modify Valve for Pressure Locking.
9641598--
2 Modify Valve for Pressure Locking.
96 42001 2
HV-0512F0168 Modify Valve for Pressure Locking.
' 96 02058 2
Elimination of Recirc Master Controller (Tiger Team).
96-02288 2
- Install Valve Performance improvement Package in 2F017A.-
96-02289.
2 install Valve Performance Improvement Package in 2F0178.
96-02290-2 Install Valve Performance improvement
- Package in 2F017C.
96 02291 2
Install Valve Performance Improvement Package in 2F017D.
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'0 ATTACHMENT 2 Page 3 d 3 Modification Unit Number Number Description 96 02784 ~
1&2 ARI EHC Backup O/S Trip Card-PO200031 --
348182 04 115-91006.
9642 2 1
Modify Valve for Pressure Locking (HV-051-IF0148).
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RECEIPT' ACKNOWLEDGEMENT FORM
.I C GS UFSAR Controlled-Cooy #~
1-11 Assigned-to :
Director-Office:of NuclearlReactor Regulation U.S. Nuclear Regulatory Commission Mail' Station 12 G18 Washington,-DC 20555 Attnt Document control Desk Please sign below as evidence of receipt of the Limerick Generating
. Station Updated-Final Safety. Analysis, Revision 07 replacement pages.
These are controlled documents that must be inserted-into
. your copy of the UFSAR.
Please take this opportunity to verify the accuracy of your-documents - by- _ conducting a self-audit.
This can be done, _ while inserting:the revision, by making _a comparison of each-individual page in your documents to the enclosed Page Revision Listing..The
- most current revision is indicated in the bottom right-hand corner of each page.
This revision number should coincide with that indicated on the Page Revision Listing.
If these controlled documents are not needed, or you wish to report missing pages, please contact the UFSAR Revision Coordinator in Licensing at the address below.
/
Signed Organization Date Return'to K.L. Moyer (610-640-6812)
PECO Energy 1 Company 62A-1, Licensing Section 965 Chesterbrook Boulevard Wayne, PA-'19087-5961
.