ML20084V048
| ML20084V048 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 05/24/1991 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20073Q515 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NYN-91084, NUDOCS 9105300034 | |
| Download: ML20084V048 (16) | |
Text
i
(
led C. Feigenbovm President ond Ch;ci Executwe Othcer NYN-91084 May 24, 1991 United States Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Document Control Desk
References:
(a)
Facility Opciating License No. NPF-86, Docket No. 50 443 (b)
New Hampshire Yankee Letter N YN-90009, dated Januaiy 8,
- 1990,
' Future FSAR Submittals," T. C. Feigenbaum to USNRC
Subject:
Submittal of Seabrook Station Updated Final Safety Analpis Report Gentlemen:
Pursuant to the requirements of 10CFR50.71(c), New Hampshire Yankee is submitting the Updated Final Safety Analysis Report (UFSAR). New Hampshire Yankee committed in Reference (b) to submit the UFSAR on or before May 26, 1991. Development of the
~
l UFSAR was in accordance with guidance provided in Generi: Letter 81-06, dated February 26, 1981. All of the incorporated changes to (Le UFSAR have been subject to review in accordance with 10CFR50.59. They reither constitute unreviewed safety questions, not alter
- he staff's conclusions as documented in the original Safety Evaluation Report or its supplements. A summary of the major revisions that have been incorporated as part of the UFSAR is attached as Enclosure 1.
The UFSAR ;6 up-to date as of December 1,1990 anc presents ch. nges made since the submittal of Amendment 63 on April 11, 1990, necessary w re fle c'
.nformation and analyses submitted to the Commission or prepared pursuant to Com,umion requirements.
Changes to tne UFSAR that were previously reported in New Hampshire Yankee's Quarterly 10CFR50.59 Reports are identified with a asterisk in Enclosure 1.
New Hampshire Yankee requests that this UFSAR submittal, specifically Chapter 17 and Appendix 17A, satisfy the reporting requirements pursuant to 10CFR50.54(a).
New Hampshire Yankee is submitting the signed origir al and ten copies to the Document Control Desk, Washington, D.C., along with a copy to the Regional Office, King of Prussi, PA and a copy to the Resident inspector at Seabrook Station. This distribution complies with the requirements of 10CFR50.4(b)(6).
New Hompshire Yankee Division of Public Service Compony of New Hompshire P.O. Box 300 = Seabrook, NH 03874
- Telephone (603) 474 9521 9105300034 910524 PDR ADOCK 05000443 K
PDR i
l t
United States Nuclear Regulatory Commission May 24,1991 Attention:
. Document Control Desk Page two if you have any questions regarding the UFSAR submittal, please contact Mr. Terry L. Harpster, Director of Licensing Services at (603) 474 9521, extension 2765.
Very truly yours, pgi /' h u m
/
Ted C. Fei enbaum TCF:TGP/ssi STATE OF NEW llAMPSHIRE Rockingham, ss.
May Mf,1990 I
Then personally appeared before me, the above named Ted C. Feigenbaum, being duly sworn, did state that he is President & Chief Executive Officer of the New ilampshire Yankee Division of Public Serviec Company of New Hampshire, that he is duly authorized to execute and file the foregoing information in the -name and on the behalf of New Hampshire Yankee Division of the Public Serviec Company and that the statements therein are true to the best of his knowledge and belief.
9mwdo E _. k b e m %
Beverly E. @loway, Notary Public)
My Commission Expires: February 28, 1995
- [v
-l United States Nuclear Regulatory Commission May 24,1991 Attention:
Document Control Desk Page three cc:
Mr, Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commission Region I ig.
475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate 13 Division of Reactor Projects
'U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior Re.ident inspector P.O. Box 1149 Scabrook, NH 03874 0
b 9
J r
l 1
+., -
__ _. 4.. _._. _.. _ _. _ _ _ _. _ _ _ _ _ _ -.. _ _ ___..._
..-..m.--
=-
m t
New Hampshire Yankee M ay - 24, 1991 3
ENCLOSURE 1 TO NYN 91084 SUMM ARY OF UPDATED FSAR CH ANGES I
4 c
r-.y--
t y
-ye,.g
.,,,,r
.+..m,..w, - -
c m
9 Format The format of the Updated FSAR ls consistent with the original FSAR with the following exceptions:
The original FSAR contained two volumes of Requests for Additional Information (RAls) and their subsequent responses.
The RAls were the result of the Commission's questions pertaining to New Hampshire Yankee's (NilY) application for an Operating License, -Information from the RAls has been incorporated into the Updated FSAR, as applicable, and thus is no longer - needed as a stand alone document.
Additionally, certain Appendices, identified by asterisks on the UFSAR Effective Page Listing were not revised, and are provided in the Updated FSAR for historical information.
Generic Chances Apolicable to All Chanters The following generic changes are applicable to all chapters of the Updated FSAR (UFSAR):
References to Unit 2, have been climinated wherever possible. Unit 2 was cancelled in 1984. The Unit 2 construction permit was allowed to expire in October 1988. It was necessa_ry to retain Unit 2 references in certain places that involved descriptions or calculations based on both units, e.g., the Exclusion Area boundary is defined as the 3000 foot radius around the Unit I and Unit 2 centerlines, and calculations such as in Tables 12.21 through 12.2 37.
Editorial revisions reflect the completion of plant construction activities and the commencement of plant operations. Terminology and typographical errors have also been corrected.
Maior Revisions by Chanter Chapter 1 Section 1.2.2, Facility Arrangement Revisions to General Arrangement (GA) Drawings. The G A drawings are included in the FSAR as Figures 1.21 through 1.2 59.
Change documents affecting the GA drawings have been tracked in the Controlled Document Tracking (CDT) System. NHY incorporated all outstanding revisions to GA drawings for this UFSAR submittal.
Section 1.3, Comparison Tables to Similar Facilities and Design Changes Since PS AR.
NRC guidance for Updated FSARs indicates that this section need not be updated. A-note has been added to this section stating that the tables have lOI
not been updated for the UFSAR, but are included for consistency with the FSAR.
Section 1,7, Drawings and Other Detailed Information The FSAR contained a listing of design drawings, including their revision numisers and date. Because NHY is regularly updating some categories of design drawings, this FSAR listing was not a reliable source for drawing status information and has been deleted. A brief description has been added to Section 1.7 explaining the NHY drawing program.
Chanter 2 0
Section 2.2.2.5(b), Pease Air Force Base Description This section has been revised to update the status of the base in response to its closure in accordance with the Base Closure and Realignment Act.
Information provided in this section provides the basis for containment design and other Seabrook Station design criteria and has been retained in its entirety.
The air traffic pattern at Pease is projected to be limited to the New
- Hampshire Air National Guard and will be significantly reduced from previous activity.
Section 2.3.3.3, Meteorological Monitoring System A description of the Backup Meteorological Monitoring System was added.
The system desc ription identifies locations, capability of its monitoring equipment, and power source independence from the Primary Meteorological Monitoring System, Chapter 3 Section 3.7(B).4.2, Seismic Instrumentation Triaxial Response Spectrum Recorder XR6708 was relocated from the Service Water Pumphouse (SWPH) foundation south corner to the SWPil electrical room, west wall, north of column 12, elevation 22' 0".
3.8.2.1,(f), Description of the Containment Penetrations The description of the fuel transfer tube assembly was revised to identify the design and fabrication codes for the new " quick closure" fuel transfer tube -
hatch, located on _the refueling canal side.
This change' also corrects the O
ASME code class and subsection upplicalile to the fuel transfer tube and its fla nge s.
7, I
i Gi Chanter 4 Section 4.3.2.6, Criticality of the Reactor During Refueling and Criticality of the Fuel Assemblics The FSAR was revised to correctly refer to the YAEC discussion of criticality of the reactor during refueling and criticality of fuel assemblies in U FS A R, Section 9.1.
The Westinghouse discussion is deleted.
Chapter 5 5.2.5.3, Leakage Detection Methods Reference was added to installation of a containment gaseous radiation backup monitor, which will act as a backup to the regular monitors. The backup monitor, along with containment sump level channel, will provide a minimum of two out of three channels required by the Technical Specifications.
Figure 5.1-1, Reactor Coolant System
\\J Drawings were updated to show re fe rcince leg connections for mid loop y
operation level transmitters and new residual heat ternoval pump suction pressure transmitters. Instrumentation enhancements are per Generic Letter 8817, " Loss of Decay llent Removal."
ChapteJJ Table 6.2-92, Containment Liner Penetrations This table is revised to add penetrations X 77 and X 78 as " essential" penetrations. These penetrations are the RVLIS tubing penetrations used for RCS wide range pressure and for the RVLIS function for post-accident monitoring.
Section 6.3.5.3, Emergency Core Cooling System Flow Indications The FSAR contained a description of Residual Heat Rernoval(RHR) pump hot leg injection flow instrumentation.
Tbc Scubrook system design does not l
)
3 xs
, --.. ~,-
-..-- - -._~_...- -.
include RHR pump hot leg injection / recirculation flow instrumentation. Table 6.3 5 is also revised as a result of this change.
Section 6.4.2.2, Habitability Systems The smoke monitoring instrumentation system is revised to identify that it is not powered or controlled from the emergency electrical distribution and is not
- ensured of power during all modes of operation as stated in the FSAR.
Section 6.6.6, In Service luspection Examination Results This section is revised to update the references to the ASME Code sections and w reflect the current status of the In Service Inspection (ISI) Program.
Chapter 7 Section 7.1.2.5, Conformance of Regulatory Guide and Section 7.3.2.2 These sections were revised to identify additional equipment that should not be tested at power so as not to damage plant equipment.
-Table 7.51, Accident Monitoring Instruction List Temperature elements for indicating the area temperature in Battery Rooms A&B were added and these elements are listed on Table 7.51.
Section 7A.12, ATWS Mitigation System A new section, 7.6.12 describes the ATWS Mitigation System. Figures were
- updated to support the new description.
+
- Figures 7.21 Functional Diagrams This revision added lag cards to the steam generator level control loops. The lag period on' the output of the steam flow / feed flow summer will provide for more stable steam generator-and feed regulation valve' operation.
d' 4
--r--~A
---nN w
c,
..---..,..c.,--
i Chanter 8
_.O; Section 8.2, Offsite Power Systems This revision reflects the installation of the Tewksbury line. The text referred to the installation of two lines prior to startup of Unit I with the third line installed prior _ to startup of Unit 2.
All three lines were installed prior to Unit 1 operation.
Therefore, the text was revised to show the actual configuration and descriptions. The forced outage rates and grid availability data are being revised to reflect the current data. The 1989 data and analysis conclude ~ that the availability factors have improved.
Section 8.2.1.5, Compliance with General Design Criterion 17 and NRC Regulatory Guide 1.32 This description was modified to clarify the two independent circuit paths as required by GDC 17. This change is required to clearly define the different connections that can be made between the UATs and the RATS to the onsite distribution system to meet the regulatory intent. This revision does not alter the original design intent and is supported by the existing Technical Specifications.
Tables 8.3 1 & 83-2, Diesel Generator Loading Sequence The diesel generator tables were revised to account for replacing'the existing nonsafety-related single phase Uninterruptable Power Supply (UPS) 14 with 4
a three phase UPS.
Chanter 9 Tables 9.1 1, 9.2 4, and 9.2 5, Spent Puel Pool These tables were upda_ted to provide revised design information on spent fuel pool heat loading according to the current design calculations.
Section 9.3.3, Equipment and Floor Drainage System Based on a review of the Station Chemistry Manual, the FSAR was updated '
to reflect present policy not to use chromates in the plant, because chromates are categorized as hazardous waste.
l.
5
-.. ~. - -
9.3.1.2, Plant Compressed Air Subsystem A discussion of the plant compressed air centrifugal compressor is added to the permanent plant design has been incorporated into this section.
9.5.1, Fire Protection System The Fire Protection Systeta description was corrected to identify that there are two (one functioning as a spare) 1500 gpm diesel engine-driven centrifugal fire pumps. This correction provides conformance with actual plant design.
Section 9.3.6, Equipment Vent System The hydrogenated vent header system description has been revised to indicate that gas from the letdown degasifier and the primary drain tank degasifier is collected.
Table 9.5 9, Listing of Unusually Hazardous Materials The table was updated to include the sodium hypochlorite storage tanks in the chlorination building on the hazardous material storage listing. This table was also-updated to reflect the current onsite gas inventory evaluation as documented by SBP 90 031.
O Chanter 10 Section 10.2.2, Automatic Controls for Turbine Trip This section was revised to incorporate an interlock to the main generator breaker trip, so_ that a manual control switch trip of the breaker causes an immediate trip of the turbine.
Section 10.4.4, Steam Dump System Valve stroke time for steam. dump valves was modified from three to five seconds for operation of full closed to full-open. This change was the result of modifications to the valves stem / bushing hardness to eliminate galling.
Section 10.4.5, Circulatory Water System This section' was modified to include two ' additional hypochlorite storage tanks -
for-chlorination when the generating cells are secured.
6
. _ _. ~. -. _ _. _
-...~. _ _.. - _. _._ _ _.__. _..
Chapter 11 Section-11.3, Radioactive Gaseous Waste System This section states that hydrogen concentration is monitored in _ cubicles containing RGWS components to detect a leak in the system. Statements have been added to clarify that monitoring is not required when the RGWS is inerted with nitrogen. This situation is acceptable since there is no potential for an explosive mixture forming in the cubicles from RGWS leakage when the system is inerted with nitrogen.
Section 11.4, Solid Waste Management System This section was revised to document the fact that an asphalt wasteform qualification program has been completed and the results accepted by the NRC.
Section 11.5, Process and Effluent Radiological Monitoring and Sampling System This section has had numerous updates as a result of a Design Basis Document (DHD) review. Minor revisions were made throughout, including Table 11.5 1.
- Chapter 12 Section 12.1.2.3, Reduction of Radiological Conditions Subsection -k was revised to reflect that the-Key Card Entry System is supplemented by barricading and/or locking to control access.
'Section 12.2, Radiation Sources
- A paragraph was added to identify which tables (Tables 12.2-1 through 12.2-37) represent information for I-or 2 Unit operation.
These tables were not revised but may be the subject for reanalysis in the future.
Section 12.3.4, Area Radiation and Airborne Radioactivity Monitoring Instrumentation-E The discussion of the spectral correctional monitor was deleted since it is no longer used.- A pontable air pump and ionization chamber detector is now used i-as the WRGM backup.
7 L
t
Section 12.5.2, Equipment, instrumentation and Facilities I
A new paragraph was added to describe the potential use of alternate health
~
physics control points for control of personnel access and radioactive materials-in addition to the established RCA control point.
Section 12.5.3.7, Storage and Handling of Radioactive Sources This section was rewritten to describe the manner in which radioactive sources are controlled, leak checked and inventoried.
Chapter 13 Section 13.1, Organizational Structure The entire section was revised to incorporate the late t organizational changes.
Section 13.2, Training
^
The training section was revised to clarify and to provide it.* necessary changes to the. training program in transition from the construcron stage to the operational stage.
Appendices A, B & D Theses appendices were deleted. Resumes for Corporate Staff (13A), Training r
Center Staff (13B) and Key Seabrook Station Staff (13D) are all available upon request thiough the Employee Relations Department.
Chapter 14 Section 14.2.7, Conformance of Test Programs with Regulatory Guides Regulatory Guide'1.79, Revision 1, Preoperational Testing of Emergency Core Cooling System for Pressurized Water Reactors; Exception to Section C.1.b,(2),
was' deleted, Testing of both trains of containment sump recirculation ~ was performed instead of only one train as identified in the. exception.
Table 14.2 5, Startup Test Abstracts i
Sheets No,31 " Calibration of Steam and Feedwater Flow Instrumentation" and Sheet No. 45 " Water Chemistry Control" were revised as requested in NRC O
8 u
.. ~.
Letter to M r. T. C.
Feigenbaum, dated December 19, 1990 ' Review of Amendment 63 to the Seabrook FSAR, (TAC No. 76712)."
Chapter 15.
Subsection 15.0.1.4,'Conditioe IV Limiting Faults Reference to a steam generator tube rupture (Subsection 15.6.3) as a Condition IV limiting fault was added.
This event has always been considered a condition IV limiting fault but was not listed.
Tables 15.0 9 through 15.0-12, Operator Actions for Different Accident Scene -ios Tables 15.0-9 through 15.012 were removed because the level of detail is greater than what is required in the FSAR. These tables represent operator actions to be taken in the event of different accident scenarios.
The inforroation in these tables is in the Emergency Operating Procedures (EOP) as reformed in FSAR Subsection 13.5.2.3.
The EOPs use the Westinghouse Owners Group derived set of guidelines as their basis.
Section 15.4.6.3, Boron Dilution Accident during Refueling This change revised the mir.imum time the shutdown margin would be lost to s
75.9 minutes and.the time for the shutdown monitor system to alarm to 32.3 minutes.
Section 15.4.8.2(e)
This revision corrected the boron concentration injected into the RCS for reactivity control. The previous amount (20,000 pfm) was changed to 2,000 ppm. This change reflects the deletion of the Baron injection Tank (BIT) as supported by NAH 90 3634, dated July -17,1990.
Chapter 16 Section 16.3, Technical Specifict tion leprovement Program This - section, was revised to incorporate -latest changes to the Production -
Technical Requirements Manual, Revision 17, Effective.3-20 91.
9 l
l..-
.. - - -. ~ -..
. _ ~ - _ -..
. _ ~ =
~(;
'L
- Chapter 17 Section 17.2.1, Organization This section was revised to reflect (be most current organization for Seabrook Station.
1 Appendix 17A, Exceptions, Alternatives and Clarifications to Program Standards, Industry
- Codes,- Federal Regulations and Guides Regulatory Guide 1.116 that endorses ANSI N45.2.81975 was revised to add a new clarification relating to the term Acceptance Criteria as used with these two documents.
Regulatory Guide 1.120 that endorses ANSI 45.2.!3 1976 was revised to add 4
an additional clarification to resolve a conflict between the guidelines of Reg.
Guide 1.123, Position C.6.e and Generic Letter 89 02 that endorsed guidance contained in EPRI NP 5652.
NOTE:' Indicates those changes previously identified in Quarterly 10CFR50.59 Reports.
i t
.--y
)
hh MEMORANDUM LICli 910549
[
'% s l'
SUBJECT RECALL OF THE ORIGINAL FSAR AND ISSUANCE OF THE NEW UPDATED FSAR (UFSAR)
FROM A. M. Callendrello I) ATE May 22,1991 TO F. G. King 02 84 In response to the requirements of 10CFR 50.71(c), New Hampshire Yankee performed a complete review and update to the Final Safety Analysis Report (FSAR),
j As a result of this review a new Updated Final Safety Analysis Report (UFSAR) was developed. The UFSAR is a complete resision of the original FSAR, including new binders, tabs, text, tables and figures. The original FSAR, Volumes 115, are to be removed from service and recycled in accordance with the New Hampshire Yankee Recycle Program.
Should you have any questions, please contact T. G. Pucko at extension 4428.
f p
V A. M. Callendrello AMC:TGP/ssi cc:
File 0061 01-48 RMD 02 06 (j, p/ 3 O
I !j,l
- v New Hompshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300
- Seabrook, NH 03874
- Telephone l603) 474 9521 0
_dU
4 9
O INSTRUCTION UPON COMPLETION OF REVIEW OF THE ATTACIIED COVER LETTER, THE LETTER SHOULD BE PLACED IN VOLUME 13, UNDER AMENDMENT IIISTORY TAB.
l u(
.