ML20215K098
| ML20215K098 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/12/1987 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20215K101 | List: |
| References | |
| CON-NRC-87-062, CON-NRC-87-62 VPNPD-87-239, NUDOCS 8706250214 | |
| Download: ML20215K098 (17) | |
Text
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'10 CFR 5 0. 71 (e)
Wisconsin Electnc eowca coursur 1
231 W. MICHIGAN,P.O. BOX 2046 MILWAUKEE, WI S3201 (414)221 2345 I
VPNPD-87-239 i
NRC-87-062 June 12, 1987 U.
S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D. c. 20555 Gentlemen:
DOCKETS 50-266 AND 50-301 PERIODIC UPDATING OF FINAL SAFETY ANALYSIS REPORT POINT BEACH NUCLEAR PLANT _ UNITS 1 AND 2 c
In accordance with 10 CFR 50.71(e), Wisconsin Electric Power Company, Licensee for Point Beach Nuclear Plant, Units 1 and 2, 4
submits the Spring 1987 revision to.the Point. Beach Nuclear Plant Final Safety Analysis Report (FSAR).. As required by 10 CFR 50.4, one original and ten copies of these revised pages are enclosed.
Each copy contains revised FSAR pages that are to be inserted in accordance with the accompanying instructions.
The information contained within the updated FSAR pages represents those changes made since our 1986 submittzt which was necessary to reflect information and analyses subnatted to the Commission or prepared pursuant to Commission requirements.
The attachment to this letter provides a description of those changes.
All changes made under the provisions of 10 CFR 59 which are included in this update have been previously identified to the Commission in the 1986 Annual Results and
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Data Report.
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PDR ADOCK 05000266
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NRC Document. Control Desk l
June 12, 19tl7 Page 2
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1 Copies of this update to the Point Beach FSAR will be submitted to the following state and local organizations:
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Public Service Commission of Wisconsin 2.
State of Wisconsin Department of Natural Resources 3.
State of Wisconsin Department of Health and l
Social Services l
4.
Town-Chairman, Town of Two Creeks l
Very truly yours, I
dI C. W.
Fa Vice President Nuclear Power l
Copies to NRC Regional Administrator, Region III NRC Resident Inspector j
Subscribed,qnd sworn to before me this l 3L M day of June 1987.
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3D urn Ms Notary Public, Stake)of Wisconsin
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.My Commission expires f 9A.
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1 ATTACHMENT DESCRIPTION OF CHANGES i
SPRING 1987 REVISION June 1, 1987 j
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Attachment June 1, 1987 Page 1
- 1. ) Grammatical, typographical and editorial errors have been corrected on the following pages:
t 1.3-17 5.3-4 7.7-22 8.2-4 12.3-1 l
2-111 Table 6.2-11 8-i 8.2-10 14.3.4-2 2.5-4 7-il 8-iii-9.6-3 14.3.4-5 2.7-3 7.7-21 8.2-2a 9.6-4 Table 14.3.4-1 2.7-4 2.) The listed drawings have been revised due to the completion of design changes or minor drawing discrepancies:
j Section 1 Section 9 (cont'd)
Figure 1.2-3 Figure 9.4-1 9.6-5 j
1.2-4 9.6-1 9.6-6 j
1.2-5 9.6-2 9.6-7 4
1.2-12 9.6-4 Section 2 Section 10 Figure 2.7-1 Figure 10.2-1 Sh. 1 l
2.7-2 10.2-1 Sh. 3 10.2-la Sh. 1 Section 4 10.2-la Sh. 2 10.2-la Sh. 3 Figure 4.2-1 Sh.1 10.2-2 Sh.1 4.2-1 Sh. 2 10.2-2 Sh. 2 4.2-la Sh. 1 10.2-2a Sh. 1 10.2-2a Sh. 2 i
Section 5 10.2-3 10.2-4 Sh. 1 Figure 5.2-19 10.2-4 Sh. 2 5.3-1 Sh. 1 10.2-4a Sh. 1 5.3-1 Sh. 2 10.2-5 10.2-6 Section 6 10.2-6a 10.2-7 Figure 6.2-1 Sh. 1 10.2-8 6.2-1 Sh. 2 10.2-8a 6.2-1 Sh. 3 6.5-1 Section 11 Section 7 Figure 11.1-1 Sh.1 11.1-1 Sh. 2 Figure 7.2-6 11.1-2 Sh.1 7.7-1 11.1-2 Sh. 2 11.1-4 Sh. 1 Section 8 11.1-5 11.1-7 Figure 8.2-1 8.2-10 Sh. 1 8.2-8 8.2-10 Sh. 2 Section 14 8.2-9 8.2-11 Figure 14.3.1-4 Section 9 Figure 9.2-1 9.3-1 9.2-2 9.3-3 9.2-3 9.3-4 J
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' Attachment' I
June 1, 1987 l
.Page 2
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3.)-.The'following pages are 'evised to reflect technical changes to the-r
-FSAR:
Section 1 Pages 1.'3-3,-1.3-8,'1.3-13 Description of Changes Changes lto these pages alter the value of the limiting Departure from Nucleate BoilingzRatio (DNBR) from 1.30 to the more generic " limit value". This change is consistent with the extensive revision of y
the FSAR in June, 1985, following initial loading of 0FA fuel, when-the identical change was made in other sections, Changes.to the FSAR relative:to 0FA fuel for that update.were recommended by Westinghouse, and were based on. analyses contained in the.0FA Reload Transition s
Safety Report, transmitted to Wisconsin Electric from Westinghs Me on September 21, 1983.
These pages.were missed in that change du-to oversight.
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' Attachment.'
June 1, 1987 Page 3-J n
Section~2 Page 2.6-2:
Description of Change l
A short paragraph was inserted in Section 2.6.1, " Meteorological Program",
- which briefly ' describes the current meteorological monitoring configura-tion for PBNP.
Also, a sentence was removed which stated that the Belfort (wind data) recorder. is installed in the control room.
The meteorological data acquisition system has been upgreded.to con-
= form to guidance proposed by the NRC in NUREG 0654 and NUREG 0737.
The system utilizes a three tower configuration.
Data from tower J
instrumentation is available in the control room.
The Belfort recorder' was.used in conjunction with the Belfort Type M wind' transmitters in establishing baseline wind. data for the PBNP site.- The sentence was l
removed because the recorder no longer exists.
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Page 2.7-3, new Table 2.7-2, new Figure 2.7-1, and new Figure 2.7-2 Description of Change The change to page 2.7-3 adds a sentence referring the reader to Table 2.7-2'and Figure 2.7-2 for a listing and physical depiction of I
the operational environmental radioactivity sampling sites surrounding.
PBNP. ' Figure 2.7-1 was changed to depict pre-operational sampling sites, while Figure 2.7-2 depicts operational sampling sites.
Table 2.7-2 is a listing of the operational sampling site locations.
Section 2.7, Environmental Radioactivity-Studies, is divided into pre-
'i operational and operational discussions.
It was observed that Table 2.7-1 listed pre-operational survey' points, while Figure 2.7-1-depicted operational sampling. sites.
The changes provide site location and depiction for both the pre operational survey sites and the operational sampling sites, 1-l l
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K Attachment
' June 1, 1987
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. age 4 p
i Section 5' i
Pages'5.1-16,'5.1-40 l
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Description of Change a
Changes'to these pages1 incorporate a description of the liner plate
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leakchase channel-(LCC)' system and provides the reference in which their consideration as an integral part of the liner plate is described..
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Page 5~.3-8 Description of Change
' Changes on this page corrected' erroneous designations of containment' radiation monitoring system (RMS) components.
The containment air particulate' monitor, previously'R-11, is now designated RE-211.
The containment noble: gas monitor (previously called the radioactive ~ gas i
monitor), previously R-12, is now designatbd RE-212.
These des'igna-tions are consistent with radiation. monitoring system descriptions' in sections 6.5.1 and 11 2.3.
(MR's IC-214, IC-215,.IC-216,10-217, IC-261, IC-319) k 4
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.I Attachment June 1, 1987 Page 5 Section 6
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Page 6.2-11 Descriptlon of Change The changes reflect the new configuration of the component cooling (CC) system heat exchangers.
The previous configuration of this shared system featured three heat exchangers - one dedicated to each unit and a shared standby or " swing" heat exchanger.
A plant modification-added a fourth heat exchanger, providing additional backup capacity and flexibility.
This configuration allows one heat exchanger to be. dedicated to each unit, with the remaining two heat exchangers being available to serve either unit.
(MR's84-157, 84-158,84-159) l 4
Attachment June 1, 1987 Page 6 Section 7 Page 7.2-11 Description of Change Two sentences were affected by this change.
The first sentence was incorrect as it previously stood, as static inverters were not a source of DC power - rather, the static inverters previously converted DC power from the station batteries to 120v AC power for the instrument buses.
This sentence was meant to describe the electrical configuration prior to system modifications in 1985 which added two new station bat-teries (D105 and 0106) and new inverters to power the white and yellow instrument buses.
The sentence, with the change, accurately describes the source of DC power as either the station batteries or the battery chargers.
The second sentence affected followed the one described above.
It was removed in its entirety due to its non-applicability (in providing amplifying information about the static inverters).
Page 7.2-18 Description of Change The change to this page alters the value of the limiting Departure from Nucleate Boiling Ratio (DNBR) from 1.30 to the more generic
" limit value".
For more information, see the Description of Changes for Section 1.
Page 7.2-23 Description of Change The change modifies the description of reactor trip breaker actuation during logic testing.
The affected sentence now states that trip breakers are actuated by both undervoltage and shunt trip coils.
This change results from the addition of auto shunt trip panels during 1986.
The shunt trip panels were installed as part of a broader modification effort necessitated by NRC requirements in Section 4.3 of " Required Actions Based on Generic Implications of Salem ATWS Events", an enclo-sure to Generic Letter 83-28.
The modification provides physical and electrical separation of A and b train reactor trip breaker control circuits, increases the reliability of the automatic trip function of the reactor trip breakers, and additionally, provides main control board indication of the bypass breakers.
84-292)
Attachment June 1, 1987 Page 7 Page 7.2-24 Description of Changes Two items were changed on this page, both providing additional inform-ation.
The first sentence was modified to include the main control board as an additional location for reactor trip bypass breaker indi-cation.
The second sentence was modified to state that the auxiliary relay - used in connection with an event recorder - is configured in parallel with both undervoltage coils and shunt trip attachments.
These changes were necessitated by modifications resulting from NRC requirements in Generic Letter 83-28, described above.
83-123,04-291 & 84-292)
Page 7.2-27 Description of Change The number of manual reactor trip pushbuttons was changed to reflect the additonal pushbuttons installed in the modification resulting from Generic Letter 83-28, described above.
84-292)
Figure 7.2-6 Description of Change This figure was changed to delete two relays and their associated contacts.
These items were shown in parallel with the undervoltage trip coils associated with the reactor trip bypass breakers (AB-1 and AB-2).
The Figure was erroneous in that two relays and associated contacts per train were shown as dedicated to the event recorder, one in parallel with the undervoltage and shunt trip coils associated with a trip breaker, and one in parallel with the undervoltage trip coil associated with a bypass breaker.
The revised figure deletes the latter contacts and relays to reflect the actual configuration.
Page 7.7-2 Description of Change Section 7.7-2, Load Dispatching, was revised to reflect actual practice.
The previous wording described the desired Point Beach unit loading (as determined by the System Control Center) as being displayed on the Reactor Turbine Generator board.
Unit loading is accomplished by licensed operatois in the control room as requested by the System Control Supervisor via telephone communication.
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Attachment June 1, 1987 Page 8 Page 7.7-9 and 7.7-9a Description of Change The description of the plant process computer was removed and was replaced with a description of the new system installed in Units 1 ara 2 during 1986.
Described is the new Plant Process Computer System (PPCS) and associated Safety Assessment System (SAS).
The Safety Assessment System was designed to meet the guidance for a Safety Parameter Display System as delineated in Supplement 1 to NUREG-0737 and the guidance in Regulatory Guide 1.97.
(MR 84-254)
Page 7.7-20 Description of Change q
Changes to the Indication section, items 1, 2 and 3 were grammatical, changing " feed" to "feedwater".
Also, new items 4, 5 and 6 were added to describe additional alternate shutdown instrumentation installed near the Unit 1 and Unit 2 charging pumps, and in the auxiliary feedwater pump room.
This modification resulted from safe shutdown RCS instrument cable routing not meeting the separation requirements of 10CFR50 Appendix R.
Figure 7.7-1 Description of Change The Control Room plan drawing has been updated to shuw the location of the new Plant Process Computer System / Safety Assessment System (PPCS/SAS) consoles 1C200 and 20200.
(MR 84-254)
It has also been corrected to show the location of the Radiation Monitoring System (RMS) control terminal and meteorological instrumentation in racks 1C103 and 1C104, and to relabel the "snackbar" as the " kitchen".
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Attachment June 1, 1987 Page 9 Section 8 Page 8.2-2 Description of Change A description of the main generator has been added to Section 8.2.2, Station Distribution System.
This change adds a description of the main generator which heretofore did not exist in Section 8.
Page 8.2-8 j
Description of Change The change is a result of a modification which provides redundant control power to the emergercy diesel generators.
Cable separation criteria of 10CFR50 Appendix R could not be met with previous cable routing, so an additional, redundant power source (station batteries 0105 or 0106) now provides control power for the diesel starting system.
(MR 84-19)
Figures 8.2-1, 8.2-8, 8.2-9, 8.2-10 Sh. 1, 8.2-10 Sh. 2 (new),
8.2-11 (new)
Description of Changes Figure 8.2-1 has been updated to reflect changes recommended by the Transmission Planning group in Milwaukee.
Figures 8.2-8 and 8.2-9 have also been similarly updated.
These figures are presently being redrawn in full scale for entry in the permanent drawing system.
Figure 8.2-10 has been renamed Figure 8.2-10 Sheet 1, and has been up-dated.
Figure 8.2-10 Sheet 2 depicts the 125 V DC distribution system associated with station batteries D105 and 0106, and partially replaces the existing Figure 8.2-11.
New Figure 8.2-11 depicts the 120 VAC Instrument Bus supply system, and also partially replaces the existing Figure 8.2-11.
Both new Figures 8.2-10 Sheet 2 and 8.2-11 are also being incorporated into the permanent drawing system.
Attachment F
b Section 9 Pages 9.3-1, 9.3-5, 9.3-8, 9.3-15, 9.3-18, Table 9.3-1, Table 9.3-5 Description of Changes i
These changes all result from a modification adding a fourth component cooling (CC) heat exchanger.
The modification was discussed in the Description of Change for Section 6, Page 6.2-11.
Page 9.3-16 Description of Change The change removes a sentence which stated that the set pressure of the component cooling surge tank relief valve is equal to the design pressure of the tank.
Modifications completed in 1986 reduced the set pressure of this valve from 100 psi to 65 psi to provide conservatism in a postulated incident where CC system pressure would rise due to leakage from the RCS system.
(4R's85-079 and 85-080)
Pages 9.6-1, 9.6-2 Description of Change Changes to these pages incorporate, by reference, the fire protection l
program presently in place at the facility.
Generic Letter 86-10, " Implementation of Fire Protection Requirements",
requires incorporation of the fire protection program, including a fire hazards analysis, by reference into the FSAR.
The reasons for this incorporation are to remsve "'icense conditions" applicable to the fire protection program and to place the fire protection program on a consistent status with other plant features described in the FSAR.
Ir, this manner, changes made to the program (not adversely affecting the ability to achieve and maintain safe shutdown) may be made under the provisions of 10CFR50.59.
Upon reporting of this change to the NRC, the licensee may also apply for an amendment to the operating license, deleting unnecessary technical specifications and incorporat-ing a " standard condition" regarding fire protection to the license.
This standard condition is spelled out in the Generic Letter.
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i-Attachment June 1, 1987 Page 11
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Page 9.6-3 Description of Change The change describes a new portion of the fire protection system as i
being seismic Class I in design.
Specifically, the sprinkler systems in the motor control center 1832 and 2832 rooms are so classified.
(MR's84-083 & 84-083-01) l Page 9.6-4a Description of Change A new paragraph was added to describe fire barrier materials for cables and raceways.
These barrier materials were added to meet 10CFR50 Appendix R separation requirements for safe shutdown required cables in the auxiliary feedwater pump room, component cooling water pump room, and Unit 1 and 2 containments.
(MR's84-022, 84-023,84-024, 84-025)
Page 9.6-9 Description of Change A sentence describing the auxiliary building ventilation system was modified.
The sentence previously stated that sufficient outside air is supplied to maintain a once through system.
This was modified to include the ability to recirculate air from the PAB central area.
This change results from a plant modification creating the recirculation flowpath.
(MR M-470) l
Attachment June 1, 1987 Page 12 1
Section 11 Pages 11.1-7, 11.1-13, 11.1-15, Table 11.1-4 Description of Changes The changes result from a modification which converted the noble gas storage tank, T20A, to a gas decay tank.
Although this tank is still connected to the cryogenic system, it will now f t.nction normally as a gas decay tank.
(MR M-708)
Page 11.2-8 Description of Change The spent fuel transfer tube shielding description has been revised.
A modification added additional shielding along the spent fuel transfer tube to reduce the potential for personnel radiation exposure during spent fuel transfer through the canal.
By strict definitir,n, a concrete thickness of 5 feet, as previously stated, is not correct for the pre-sent configuration.
(MR 83-103)
Attachment June 1, 1987 Page 13 Section 14 References - Section 14.3.4 Description of Changes The proper references to Section 14.3.4 have been added.
They were missing previously, although they were still referred to in the text of.Section 14.3.4.
A check of the Final Facility Description and Safety Analysis Report (FFOSAR), which preceded the FSAR, revealed that the references were also missing in that document.
Westinghouse Corporation provided the references upon request.
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Attachment June 1.,'1987-Page'14 Appendices Appendix B i
Table 1 j
Description of Change The change is a result of a modification which added a fourth component cooling (CC)' heat exchanger.
See the Description of Change for Page 6.2-11 for additional details.
Appendix E Page E-1 Description'.of Change The change to the first sentence of the Introduction paragraph deletes reference to the Nuclear Regulatory Commission information request titled " General Information Required for Consideration of. the Effects of a Piping System Break Outside Containment".
Appendix E was written'in response to the above information request.
Regarding Criterion 1, the definition of a "high energy piping system" i
was in question. -The above.information request defined it as a system where_ pressure is greater than 275 psig or temperature is above 200 F.
However, the actual criterion under whicli~the analysis was performed used a definition of greater than' 275-psig and above 200 F.
This-definition is documented in the NRC's Safety Evaluation Report dated May 7, 1976.
To' eliminate the discrepancy between the Introduction paragraph and' Criterion 1, reference to the information request was deleted.
The reference does, however, still exist in Appendix E as " Reference 1",
on the Reference page at the end of the Appendix.
Appendix I Pages I.1-5 and I.2-7 Description of Changes The changes to these pages resulted from a modification which reestab-lished the noble gas storage tank (T20A) as a gas decsy tank.
The modification is further discussed in the Description of Change to Section 11.1.
(MR M-708)