ML17055C123
| ML17055C123 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/24/1986 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Bernero R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17055C124 | List: |
| References | |
| (NMP2L-0793), (NMP2L-793), NUDOCS 8607300122 | |
| Download: ML17055C123 (118) | |
Text
ACCESSION NBR:
'- uFAC IL: 50-410 AUTH. NAIIE NANQAN. C. V.
REQULAT INFORHATION DISTRIBUTION STEN (RIDS) 8607300122 DOC. DATE: 86/07/24 NOTARIZED: YES DOC)MT N Nine Nile Point Nuclear Statione Unit 2e Niagara I'toha 05000410 AUTHOR AFFILIATION Niagara.a Nohatok Power Corp.
RECIPIENT AFFILIATION Division of Boiling Water Reactor (BWR) Licensing 1
0 0
1 3
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SUBJECT:
Forlllards Amend 27 to FSAR for Nine Nile Point Nuclear Station Unit 2e including proprietary Section hA. Amend submitted per 10CFRSO. 30(c)(1) 8c NRC 830329 Itr. Section hA withheld Ieee IOCFRE. 790).
DISTRIBUTION CODE:
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TITLE: Licensing Su mittal:
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V HIIASAIRA U MQNIAWK NIAGARAMOHAWKPOWER CORPORATION/300 CRIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 July 24, 1986 (NMP2L 0793)
Mr. Robert Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Bernero:
Re:
Amendment 27 to Application to Operating License Nine Mile Point Unit 2 Docket No. 50-410 In accordance with 10 CFR 50.30(c)(l) and your March 29, 1983 letter, enclosed are three originals and 60 copies of Amendment 27 to the Final Safety Analysis Report.
These changes incorporate certain responses into the text of the Final Safety Analysis Report.
Also included are changes that have resulted from our continuing review of these documents.
In the original submittal of the Final Safety Analysis Report on January 25, 1983, we requested proprietary status for certain figures in Section 6A in accordance with 10CFR2.790.
The September 21, 1983 letter from A. Schwencer to G. K. Rhode approved this proprietary status.
Amendment 27 contains updates to a figure in Section 6A.
Also enclosed is the Summary of Incorporated Changes.
This list is to assist the Nuclear Regulatory Commission in reviewing Amendment 27.
Very truly yours, JM:ja 1853G Enclosures C. V. Mangan Senior Vice President
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W. A. Cook, NRC Resident Inspector Project File (2) r Bb07300122 Sb0724 PDR ADOCK 05000410 K
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
Niagara Mohawk Power Corporation
)
(Nine Mile Point Unit 2)
Docket No. 50-410 AFFIDAVIT C. V.
Man an
, being duly sworn, states that he is Senior Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.
Subscribed and sworn to before me, a Notary P+ublic in and f'r the State of New York and County of
, this ~H day of 1986.
Notary Public in and for a.
- County, New York My Commission ex'.ires:
CHRISTNE AUStN Hotayv Public in the State ot Neo York ualifet in Onondaga Co. NL 4181M@
mission Expires March 30, Ills
1H
),life,.",..)g~,))q t
Nine Mile Point Unit 2 FSAR
SUMMARY
OF INCORPORATED CHANGES Legend
Response
to NRC guestion or request, or SER Item.
Editorial or typographical change that has not affected basis of FSAR.
Nonsafety-related change in design,
- schedule, and/or procedure.
SN -
Change to a safety-related item that has no effect on SER.
=
Change to safety-related item that could affect the SER.
TS -
Change that affects the Technical Specification.
Amendment 27 1020-12177-HC3 SIC-I 3uly 1986
0
~Pa es Attachment 1.9-61 Page 2.4-28 Pages 5.3-6, 5.3-7, 5.3-21 Page O'ER F251.1-2 Pages 6.2-85, 6.2-86 Table 6.2-56, Sht.
7 Page 8.3-24b Table 8.3-3A Table 9.5-3, Sht.
9a Page 9A.3-16 Page 9A.3-18 Change Code R,
TS R,
TS Descri tion Incorporate description of testing of fire boot type penetration seals that deviates from SRP 9.5-1 (Letter No.
NMP2L 0740 dated June 10, 1986).
Correct number from 16 to 15 public water supplies, consistent with Table 2.4-9.
Though there are a
total of 16 supplies listed in the
- table, one is an industrial use only'evise the FSAR to be consistent with the technical specifications relative to the material surveillance program and change wording referring to lead factors (Letter No.
NMP2L 0745 dated June 11, 1986).
Replace "exemption" with "exception" in accordance with NRC request.
Provide mark numbers for the TIP system ball and shear valves in accordance with NRC staff requests Cl ar ify 1 oc at ions of HPCS di es e 1 generator annunciations (i.e.,
main control room or diesel generator control room) as requested by the NRC staff.
Incorporate deviation to NFPA 80 relative to nonlisted fire door hardware (Letter No.
NMP2L 0740 dated June 10, 1986).
Clarify that manual local application C02 systems are provided for turbine lube oil piping located above the turbine deck (Letter No.
NMP2L 0512 dated October ll, 1985).
Clarify that the fire pumps are not safety related (Letter No.
NMP2L 0512 dated October ll, 1985).
Amendment 27 1020-12177-HC3 SIC-2 July 1986
P
/.
~Pa es Page 9A.3-31 Change Code Descri tion Delete the requirement that fire brigade members have knowledge in safety related systems.
This requirement is discussed in another paragraph.
Correct procedure number from APN-10P to NTP-5 (Letter No.
NMP2L 0512 dated October 11, 1985).
Table 9.8.8-1, Shts.
66, 75 R
Page 10.2-3a Page 11.4-4 Page QER F210.38-2 Page Q8R F280.23-1 Table 421.36-1, Shts.
1, 2,
14 Add additional description of the concrete wall separating unit coolers 2HVR*UC413A and 2HVR*UC413B (Letter No.
NMP2L 0740 dated June 10, 1986).
Revise main steam system valve testing frequency to be consistent with the technical specifications by deleting statements on testing and inserting reference to the technical specifications.
Correct radwaste backup system line sizes (Letter No.
NMP2L 0719 dated May 19, 1986).
Update response to Question F210.38 to reflect inclusion of the subject snubber examinations in the PSI inspection plan and the initial test program.
Response
revised to reflect completion of evaluations regarding effects of water damage due to fire fighting activities on the ability to safely shutdown.
Add two additional instruments for reactor vessel level (wide range) measurement (Sht.
1), correct the mark numbers for AAS containment isolation valves (change N to H)
(Sht. 2), correct mark number for instrument measuring cooling water flow to the Div.
2 diesel generator (Sht.
14).
Amendment 27 1020-12177-HC3 SIC-3 July 1986
0~f
/
~Pa es Pages Q&R F430.71-1 Q&R F430.36-2 Pages QER F430.44-1, Q&R F430.49-1 Pages QER F492.7-1, 2
Pages QER F421.23-2, 3
Page QER F620.1 Change.
Code Descri tion Revise responses to Questions F430.36, F430.71 to reflect completion of installation of the heavy-duty turbocharger on the Division III diesel generator.
Revise responses to Questions F430.44 and F430.49 to reflect that eight-hour battery pack lighting has been provided.
Update response to Questions F492.7 and F421.23 based on completion of the subject evaluations of water level sensing instrumentation.
Update response to Question F620.1 to delete the commitment for future updates'hange "will submit" to "has submitted."
Page Q&R F620.01-1 Page Q&R F620.05-1 Page QER F640.34-4 Page SSC-6 Update response to question F620.01, Item a to reflect submittal of the document under separate cover.
Update response to Question F620.05 to delete commitment on updating FSAR Section 1.10, Items I.D.l and I.D.2 that has now been completed.
Revise response to Question F640.34, item l.i (10).
Containment and suppression pool vacuum breakers will be tested as part of the containment purge (not isolation) system preop testing.
Revise response to Item 13 to reflect that system design drawings were provided and reviewed as required during the Appendix R
audit..9-15 Typographical error.
Change 3.05m to 3.0 Sm.
Amendment 27 1020-12177-HC3 SIC-4 July 1986
7
~Pa es.9-37, Sht
~
1 Change Code E
Descri tion Correct table refe'rence from 5.2-3 to 5.2-5.
Replace "as" with "and code cases."
Change notes to noted.
Change code case N-207 to N-1588.
Attachment 1.9-78 Delete last sentence concerning nonapplicability of other tasks to Unit 2.
All referenced tasks have been addressed.
Page 1.10-101 Page 1.12-11 Page 2.5-167 Correct spelling of "studies."
Revise discussion of water leg pump operation for clarity by clearly stating that a static column of water cannot induce air into the fluid system.
Add "The locations and" at the beginning of the sentence referencing Figures 2.5-94 through 2.5-96.
Page 2.5-167b, Figures 2.5-96E, 2.6-96F Page 2.5-194b Pages 3.1-34, 3.1-47 Pages 3.6A-5, 3.6A-37, Tables/Figures Reference Page Table 3.68-2 Page 3.7A-7 Add clarification to dowel length description (p
2 '-167b).
Delete dowel length dimensions from the figures.
Add subscript t that was inadvertently omitted.
Editorial clarification (p 3.1-34).
Del ete reference to GE valve number that is not necessary.
Add the word "inspection" (p 3.1-47).
Revise figure number from 3.6A-51 to 3.6A-49 consistent with the actual figures to be provided.
Correct number from 4.62 to 4.206 for break RC4LL.
Rearrange the paragraph describing the portions of the diesel generator building floor slabs beneath which granular fill was placed, for clarity.
Amendment 27 1020-12177-HC3 SIC-5 July 1986
0>>
n
~Pa es Table 3.8-5 Table 3.8-6 Table 3.8-7 Change Code Descri tion Add missing 4
- symbol, change Sm to Sn in several places.
Correct alignment of several stress limit equations with the corresponding load combinations (Sht.
1).
Clarify load RT to include jet impingement effects, if applicable (Sht. 2).
Change OBE to OBEI and SSE to SSEI (Sht. 1).
Correct Sn top (Sht. 2).
Page 3.8-37 Change ~
to ~
This was inadvertently changed in Amendment 26.
Pages 3.9A-9, 3.9A-15, 3.9A-21 Add the words "criteria and" in first paragraph (3.9A-9).
Delete "safety" in references to the ASME code (3.9A-15).
Revise "generically" to "generally" (3.9A-21).
Figure 3A.22-1 Page 4.1-5 The figure is deleted.
It is not referenced in Section 3A.22 and is not needed to describe the PITRUST program.
Correct section cross reference from 4.2.2.1 to 4.6.1.1.
Page 4.6-3 Figure 5.1-2, Shts.
1, 2, 3
E Page 5.4-41 Page 6.2-74 Table 6.2-3, Sht.
2 Table 6.2-9 Editorial.
Change low to local.
Renumber the sheet numbers to put the figures in the proper order.
Delete "drawoff" from system name.
Editorial.
Item ll is redundant to Item 3 on page 6.2-73.
Make "chambers" singular and add comma in Item 2 under Vacuum Breakers heading.
Change recirculation loop to loops.
Amendment 27 1020-12177-HC3 SIC-6 July 1986
)
~Pa es Table 6.2-15, Sht.
1 Change Code Descri tion Correct type in number for Item 2c, 23.40 column.
Table 6.2-56, Sht.
6 Reinsert closure time for valve 2ICS*MOV121 that was inadvertently omitted in Amendment 26.
Figure 6.2-50 Correct y axis title.
Should be GPM.
Figures 6.2-68A, 6.2-69 Feedwater line break node model numbers reversed in titles.
Page 6.3-16 Page 6.3-31 Replace "wall" with "penetration."
Correct figure reference from 5.4-15 to 5.4-14.
Page 7.3-20 Correct figure reference from 6.5-2 to 6.5-1.
Pages 7.6-4, 7.6-22 Figures 7.6-7, 7.6-8 Page 7.7-23 Pages Q&R F421.13-1, 5
Page QER F421.20-2 Page 8.1-2 Correct figure reference from 7.6-5 to 7.6-4 (p 7.6-4).
Correct section reference from 7.1.2.4 to 7.1.2.3 (p
7 '-22).
Correct dimension from 12 to 2 in.
(F 7.6-7).
Place K10 and K12 relays note in the legend box.
Correct figure reference from 7.7-7 to 7.7-6.
Correct spelling of Validyne.
Correct mark numbers of condensing chambers by changing B21 to B22.
Revise total NMPC grid system capability from 6924 to 7056 MW, and firm purchase commitment from 1963 to 2039 MW.
Pages 9.3-23, 9.3-25 Figures 9.3-13, Sht.
1; 9.3-14, Shts.
1, 3; 9.3-15, 9.3-16, Sht.
6 Alternating of sump pump operation in sumps provided with duplex sump pumps will be accomplished with a manual selector switch rather than an electrical switching system.
Amendment 27 1020-12177-HC3 SIC-7 July 1986
lg
~Pa es Pages 9.3-26a, 9.3-27 "Change Code Descri tion Add Item 21 indicating local control for the diesel generator floor and equipment drain sump pumps (9.3-26a).
Clarify that the sump pumps (not the sumps) discharge to the storm sewer (9.3-27).
Page 9.5-65 Auxiliary boiler system safety valves discharge to contact condensers, not condensate storage tanks.
Correct safety valve mark number (change 5 to 2).
Figures 10.1-4a through 10.1-4d Figures 10.1-7a through 10.1-7w Update moisture separators and reheaters P&ID.
Editorial corrections.
Incorporate various as-built conditions.
Add a check valve downstream of the moisture separator drain receiver tank as added protection against backflow.
Update feedwater heater systems and extraction steam systems P&ID.
Editorial and drafting corrections.
Incorporate various as-built conditions, Pages 10.3-2, 10.4-9 Page 10.4-17 Revise to reflect that turbine gland sealing steam cannot be-supplied by the auxiliary boilers.
Clarify that circulating water constituent concentrations are maintained as a result of constant makeup and a controlled blowdown flow.
Page 10.4-27 Table 10.4-2 Clarify interlocks description for starting the chemical waste sump pumps by deleting the word "not" in two places and replacing and with or Delete entry for alkal inity as CaCO and clarify the
- footnote such that all table values are two times the concentration of the normal lake water.
Amendment 27 1020-12177-HC3 SIC-8 July 1986
P'
~Pa es Table 11.2-1, Sht.
2 Figures 11.4-1a through 11.4-lh Table 1.8-1, Sht.
44 Table 1.8-1, Sht.
119 Page 1.10-64h Page 1.12-37 Figure 2.5-188 Table 3.2-1, Sht.
3 Table 3.2-1, Sht.
9 Change Code SN SN SN SN Descri tion Include identification for the third waste collector
- pump, 1C.
Update radioactive solid waste system PE ID.
Editorial/drafting corrections and incorporation of minor as-built changes.
Revise compliance statement for Regulatory Guide 1.43 to be consistent with the discussion provided in FSAR Section 5 '.3.3.2.
Update the compliance statement for Regulatory Guide 1.105 to reference Revision 2 of the guide.
Provide previously missing value for design basis activity of the reactor coolant sample.
" Delete paragraphs discussing bolts, which is not the subject of Licensing Issue 54.
FSAR Section 3.9B discusses design of bolts, Update the west berm subsurface profile based on the actual berm configuration.
Revise quality group for SLCS explosive values from A to B, and clarify piping description as being upstream or downstream of the containment valves rather than the explosive valves, consistent with the actual plant design.
Correct RHCU system heat exchanger cooling water side quality group classification from D to C.
Table 3.2-1, Sht.
14 Table 6.1-1, Sht.
1 Page 6.2-77 SN Incorporate description of strainers provided for the H2 recombiner cooling water.
Amendment 27 1020-12177-HC3 SIC-9 July 1986
I
~Pa es Table 3.2-1, Shts.
15,
- 15a, 16 Table 3.2-2 Tables 3.4-2, Shts.
1, 3; 3.4-5, Shts.
1, 2
Change Code SN Descri tion Update location and tornado pro-tection column entries for auxiliary ac power system items based on actual equipment locations.
Update location for 125V DC power system.
Revise seismic category to NA for emergency cables.
Clari fy Note 6 regarding des i gn standards utilized for NSSS-supplied versus BOP-supplied quality Group D pumps.
Replace EB-15 designation with HVR in system column, and define HVR (T3.4-2).
Replace TBCLCW designation with CCS in system
- column, and replace "spare" with "abandoned" for sleeves W1243C and W1244C (T3.4-5).
Figures 3.6A-50 through 3.6A-60 SN Miscellaneous corrections to elevations and piping ID numbers based on as-built conditions.
Also, corrections to figure cross-references.
Page 3.6B-,9a Page 3.7A-32 Page 3.8-76 Table 3.8-15, Sht.
1 SN Cl ari fy the use of CT 2.0, which is generally used unless otherwise justified
~
Clarify that activation of the containment mat response spectrum annunciator occurs when preset g-'levels at corresponding frequencies are exceeded.
Include hand calculations as a
method of analysis for foundations of Category I structures.
Delete 326.8 ft entry and add vert)cal displacement value for the 322.5 ft entry, to be consistent with the actual test results.
Page 3.9A-26b SN Delete reference to SA-449 high strength bolts, which have not been used.
Amendment 27 1020-12177-HC3 SIC-ID July 1986
~Pa es Table 3.9A-S, Sht.
2 Table 3.98-2s, Sht.
2 Page 3.10A-5 Change Code SN Descri tion Correct subscripts in the definitions of loads SRVALL SRVpNE and SRVADS Revise RCIC turbine nozzle calculated
- loads, FR and MR, based on completion of stress reconciliation.
Clarify that cable tray supports may use pinned connections to the structural members.
Pages 3A.9-1 through 3A.9-4, SN 3A.9-6, 3A.10-1, 3A.10-2, 3A.10-3 Table 3A.10-1 Figure 3A.10-4 Update descriptions of the LIMITA2 and LIMITA3 programs based on the programs currently in use.
Figure 3A.12-1 Pages 3C-6, 3C-12, 3C-lla Pages 3C-24 through 3C-28 3C-30, 3C-32, 3C-33, 3C-34 Tables 3C.4-1 through 3C.4-4, 3C.5-1 SN SN Revise the target,
- sources, and angles to be consistent with the data in Table 3A.12-1.
Correct pipe elevations from 250 ft to 253 ft 4 3/4 in (3C-6) and from 343 ft 2 in to 342 ft 8 ll/16 in (3C-12) and 342 ft 10 5/8 in to 338 ft 9 1/16 in (3C-lla) based on as-built conditions.
Update HELB and MELC spray and flooding evaluation discussions.
Junction and terminal boxes subjected to spray to have NEMA 12, drip proof enclosures, rather than NEMA 4 (3C-24).
Revise single failure evaluation guidelines in Item 10 consistent with actual analysis methodology (3C-25).
Change tense from "will be" to "are" regarding protection of components from spray, and include statements regarding junction boxes (3C-26).
Clarify that no targets required for safe shutdown are in piping tunnels, change tense from "will be" to "are," include junction boxes as potential
- targets, and incorporate previously missing discussion for the standby Amendment 27 1020-12177-HC3 SIC-11 July 1986
/g
~Pa es Change Code Descri tion gas treatment building'(3C-27).
Delete the exception regarding a
scram discharge volume crack (3C-28).
Incorporate Item 10 describing assumed visual leak detection and leak detection provided for specific areas, and revise orifice coefficient from 0.82 to 0.6 or higher (3C-30).
Change "will be" to "have been,"
revise the reactor building general floor area discussion based on identification of a MELC in an 18 in'HR line as the limiting case for flooding, and include visual inspection as a means of leak detection (3C-32).
Delete mention of water level sensing devices and replace with visual detection within 8 hrs. for the control building, and revise piping tunnel discussion of flooding effects on service water system equipment in the piping tunnels (3C-33).
delete the phrase regarding 1/4 in. of water for detection plus 30 min.
operator action, revise discussion of flooding of one screenwell building pump bay based on physical separation and visual detection at 8 hr.,
and provide previously missing discussion for the standby gas treatment building (3C-34).
Revise system design pressure and maximum flooding leakage rate for RDS and SFC systems (T3C ~ 4-1).
Revise system design pressure for the HVK system, system design temperature for the DWS system and all maximum flooding leakage rates (T3C.4-2).
Revise system design pressure for the SWP.system, temperature for the EGF system, and maximum flooding leakage rate for both the SWP and EGF systems (T3C.4-3).
Revise maximum flooding Amendment 27 1020-12177-HC3 SIC-12 July 1986
Ip n
~Pa es Change Code Descri tion leakage rates for all systems except
Delete the scram discharge volume break entry from Table 3C.5-1.
Page 4.5-5 Page 4.5-8 Page 5.4-27 Page 6.1-1 Table 6.1-3 SN SN SN SN Add nuts to listing for core plate studs and correct material type from ASME SA-276 to A-276.
Clarify that the reactor internals purchase orders were placed prior to issuance of Revision 2 to Regulatory Guide 1.31.
Clarify that isolation conditions are those isolations of the primary system requiring RCIC operation.
Clarify the last sentence.
Periodic testing of the valve requires parts replacement, nest replacement of the valve.
Delete listing for Devcon plastic steel A and revise quantity for shimming material from 475 to 300 lb.
Pages 6.2-49, 6.2-50, 6.2-51, 6.2-52, 6.2-53, 6.2-57, 6.2-57a SN Clarify that the secondary contain-ment is maintained at a negative pressure of 0.25 in. N.G. (6.2-49, 6.2-57a).
Delete statement regarding Regulatory Guide 1.52.
Compliance with this guide is addressed in Section 6.5.1.
Change valves to dampers (6.2-50)
~
Revise Item 3 on page 6.2-50 and Item 8 on page 6.2-51 to eliminate duplication and to clarify the reactor building structural design.
Delete discussion of the reactor building ventilation system (HVRS).
A complete description is provided in Section 9.4.2 (6.2-52)
~
Clarify operation of the HVRS during accident conditions.
Amendment 27 1020-12177-HC3 SIC-I 3 July 1986
~r,
~Pa es Page 6.2-75a Page 6.2-83 Page 6.2-84 Page 6.2-88 Tables 6 '-60, 6.2-61 Figures 6.2-89, 6.2-90 Table 6.2-3, Sht.
1 Change Code SN SN SN, TS Descri tion Delete "butterfly" from description of ventilation system dampers (6.2-53).
Delete discussion of SGTS lines penetrating the reactor building., The SGTS is fully discussed in Section 6.5 (6.2-53).
Delete phrase "which is at uniform pressure" (6.2-57).
Clarify that the recombiner draws air from both the drywell and the suppression chamber.
Revise the description of interlocks provided for the H2 recombiner skid cooling water block valves.
They are now interlocked with the recombiner discharge line containment isolation valves instead of the gas blower.
Add discussion of the strainer blowdown drain valve interlocks.
Clarify controls for the recombiner air inlet and cooling water inlet'alves, Only the cooling water inlet valves are controlled automatically.
The air inlet valves are manually closed.
Delete Item 14.
Recombiner cool ing water or air inlet valves motor overload alarm has been deleted from the design.
Incorporate description of the low pressure drywell bypass leakage test.
High and low pressure tests will be conducted by monitoring pressure decay rather than actual leakage.
Also, drywell to suppression chamber P revised from 25 to 25 + 0.5, -0.0 psi (6.2-88, T6.2-61).
Change Pt to Pa to be consistent with technical specification terminology (T6.2-60).
Correct 200'F to 293'F, which is the saturation temperature corresponding to a pressure of 45 psig.
Amendment 27 1020-12177-HC3 SIC-14 July 1986
r~
~Pa es Table 6.2-37 Table 6.2-57 Table 6.2-56, Sht.
22 Figure 6.2-10 Figure 6.2-70, Shts.
10, 16, 17, 22 Change Code SN SN SN SN SN, Descri tion Correct two values in total effective break area column from 1.736 to 1.030 consistent with current analysis.
Correct maximum containment pressure for recombiner operation from 13.3 to 21.3 psig.
Under Monitoring Systems, change "systems" to "loops," change operation from continuous to manual.
Clarify Note (22).
Flow indication is provided only for flow entering the hydrogen recombiner.
The recombiner will shut down automatically if gas flow drops below 50 percent of normal flow.
Correct scale numbers on y axis.
Delete test connection not currently in the design (Sht.
10); move, test connection location to the valve body (Sht.
16), correct mark number for valve 2RHS*V143 (Sht.
17),
correct location of hose connection (Sht. 22).
Figures 6.2-71a, 6.2-71b Table 6A.10-2, Sht.
1 SN SN, TS Update containment atmosphere monitoring system PAID.
Editorial corrections and incorporation of minor as-built changes.
Add implementation of NUREG-0737, Item II.B.3 requirement for taking grab samples.
Incorporate flexible hoses in various instrument lines to accommodate differential movement between the primary and secondary containment structures, group hydrogen and oxygen analysis into a single unit to facilitate operations.
Correct the maximum service water temperature from 77 to 76'F consistent with the technical specifications.
Amendment 27 1020-12177-HC3 SIC-15 July 1986
I
~Pa es Table 7.1-2, Shts.
1, 3
Change Code SN Descri tion Revise note references, including addition of Note 10, clarifying the comparison between Unit 2 and Zimmer-1 for the containment and reactor vessel isolation control system.
Unit 2 uses ball type MSIVs.
Zimmer does not.
Page 7.2-21 SN Reference Ch.
15 for discussion of failures.
Page 7.3-5 Page 7.3-34 SN SN Cl ar ify discussion of AOS permissive signal.
Replace "logic channel" with "trip system" and "system" with "pump."
Delete the word "all" in regard to simulation of actions resulting from actuation of the system level manual initiation switches.
Pages 7.4-3, 7.4-4 Table 7.4-1 Pages 7.5-1, 7.5-2, 7.5-5 SN SN SN Reference Ch.
3 for environmental qualification of RCIC and
- SLC, system components.
Correct instrument ranges based on actual supplied instruments.
Change RCIC system pump low suction pressure from 0-300 psig to 30 in Hg vacuum 0 psig, RCIC system steam supply low pressure from 0-300 psig to 0-1500 psig, and RCIC system pump discharge pressure high from 0-3000 to 0-1500 psig.
Add listing from RCIC system pump high suction pressure.
Correct references to NUREG 0737 task item numbers.
Table 7.5-1, Sht.
1 SN Correct reactor vessel water level range from "-150-0-60 in" to "-5 to 205 in" per latest design information.
Page 7.6-7 Change "less" to "greater" regarding turbine first-stage pressure setpoint.
Amendment 27 1020-12177-HC3 SIC-16 July 1986
~Pa es Page 7.6-17 Page 7.6-18 Change Code SN SN Descri tion Clarify the environment qualification of NMS equipment, consistent with letter NMP2L 0589 dated January 20, 1986.
Delete "relays" in description of isolation devices.
Page 7.6-20 Table 7.6-1 Table 7.6-3, Sht.
2 SN SN Replace "channel" with "APRM or IRM" to clarify operation of the bypass switch.
Correct instrument ranges.
Change RHR shutdown cooling isolation pressure from 0-3000 to 0-1200 psig and RHR steam condensing mode steam line pressure high from 0-1000 to 0-500 psig.
Change RCIC steam supply line flow high range from 0-600 to 0-750 in.
H20 based on actual supplied instrument.
Table 7.6-5 Table 7.6-6 Page 7.7-8 Page 7.7-13 SN SN Correct instrument ranges.
Change LPRM downscale and LPRM upscale from "2 percent to 0" to "0 to 125 percent full scale."
Update APRM system instrument data.
Clarify trip versus alarm functions.
Revise APRM downscale alarm range to 0 to 125 percent full scale (4 percent nominal) and APRM upscale (neutron trip) to 0 to 125 percent full scale (118 percent nominal).
Change red to white light display for APRM inoperative.
Clarify the effect of the IRM range switch on initiation of a rod
- block, items 4a, 4b, 4c.
Change main control room "lights" to "indicators."
Page 7.7-22a SN Change "fully" to "greater than 90 percent" consistent with the actual system design.
Amendment 27 1020-12177-HC3 SIC-17 July 1986
/
~Pa es Page 8.3-13 Figure 8.3-3, Sht
~
2 Change Code Descri tion Panel designations changed from 2VBS*PNLA101 and 2VBS*PNLB101 to 2VBS*PNLA100 and 2VBS*PNLB100.
Page 8.3-40 Table 8.3-3, Sht.
2 Table 8.3-4, Sht.
3 Page 9.3-31 SN SN Include control circuits for dual protection in discussion of instrumentation circuit penetration current carrying capabilities.
Include control feeders in discussion of electrical penetrations provided with primary and backup protective devices.
Include the two hr. rating for the HPCS diesel generator.
Revise the listing for the Div. III (HPCS) diesel generator.
Change rating from 2600 to 2850 kw (the 2000 hr rating), volts from 4000 to
- 4160, and full load amps from 376.8 to 378.
Pages 9.3-3, 9.3-4, 9.3-7 Page 9.3-24 Page 9A.3-52 SN SN SN, TS Correct dewpoint lower range from 39 to 35'F (p. 9.3-3).
Correct low pressure setpoint for lag compressor start from 100 to 90 psig and the selected backup unit automatically starts when the header pressure further decays below 85 psig, not 100 psig (p.
9.3-4).
Revise description for service air system block valve operation.
Valve can be opened locally if low-low pressure condition does not exist.
Valve closes automatically on low-low pressure (p. 9.3-7).
Clarify that equipment and floor drain piping is evaluated as to the need for seismic design/support, not just the supports.
Revise fire hose testing requirements to be consistent with the technical specifications.
Amendment 27 1020-12177-HC3 SIC-18 July 1986
~Pa es Tabl e 12.3-4 Page 15.1-4 Change Code Descri tion Update certain dose rate values consistent with currently calculated values.,
Delete incorrect phrase regarding peak fuel center temperature of 588'F.
Page 15.1-8 Page 15.1-12 Table 15.2-12 SN SN Correct 1020 to 1010 psig as the pressure corresponding to 155 percent NBR feedwater flow.
Delete incorrrect phrase, "just slightly below the set point of the first pressure relief group."
Revise time for initiation of controlled depressurization from 33.2 to 33 min. consistent with current analysis.
Page 15.3-8 Page 15.4-15b SN Delete incorrect statement regarding performance of the analysis with a single or two loop pump seizure.
Revise results to indicate that the MCPR remains above the safety limit, and delete the phrase concerning the MLHGR, consistent with current analysis.
Table 15.4-8 SN Revise fuel loading error analysis results to be consistent with analysis.
MCPR with misplaced bundle revised from 1.14 to 1.13.
CPR for event revised from 0.10 to 0.11.
Pages 1.10-86, 1.10-91 Pages 1.10-95, 1.10-96 SS SS Update to reflect completion of the indicated modifications to the ADS and RCIC initiation logic.
Delete reference to the intertie between the service water and RBCLCW systems, which has been Amendment 27 1020-12177-HC3 SIC-19 July 1986
c
~Pa es Table 3.2-1, Shts.
14, 15,
- 26f, 26g Change Code SS Descri tion deleted.
However, during a loss of offsite power, cooling water flow to the idle RCS pump seals can be established via the CRD pumps.
Include penetrations Z328-3 and Z-45 to the list of items not certified on the N-5 Code Data Report.
These are extensions of primary containment for nonsafety related systems.
Add Note 41 reference on Sht.
15 that was inadvertently omitted in Amendment 26.
Page 3.4-3 SS Delete statement concerning sump pumps and/or drains.
The intake and discharge building, el.
224 ft., is not provided with sump pumps or drains.
Pages 3.5-4, 3.5-4a, 3,5-4b, SS 3.5-4c, 3.5-5, 3.5-5a, 3.5-5b Incorporate discussion of hydrogen,
- oxygen, and nitrogen compressed gas cylinders as potential missiles, including Justification for why they are not credible missiles.
Page 3.9A-11 Tab 1 e 3. 9A-4 Page 3.9B-16 SS SS SS Include pneumatic and hydraulic valve actuators that are qualified by dynamic testing (Item 4).
Incorporate statement regarding qualification of valves by analysis only.
Clarify acceptance criteria 1 for cases where the TRS does not envelop the RRS.
Update the BOP seismic/dynamic qualification results summary for mechanical equipment based on completion of the qualification program.
The self-cleaning strainers, guideline IEEE 334-1975, should go to 334-1974.
Revise Section 3.9.1.2.3B to describe use of the ANSYS code in analyzing the recirculation pump
- casing, Amendment 27 1020-12177-HC3 SIC-20 July 1986
r
~Pa es Page 4.5-3 Page 5.3-6 Page 6.1-2 Change Code SS SS SS Descri tion Delete statement concerning dye penetrant examinations, which have not been performed.
Include references to 10CFRSO Appendix G requirements concerning pressure/temperature limitations.
Revise to indicate that painting of stainless steel may be permitted provided that the paints do not contain contaminants that would be harmful to the stainless steel.
Pages 6.2-46a, 6.2-46b Tables 6.2-51, 6.2-S2 Figures 6.2-40, 6.2-41, 6.2-42, 6.2-43 Pages 6.2-54, 6.2-54a, 6.2-54b, 6.2-55a, 6.2-55b Tables 6.2-55a, Sht.
2; 6.2-55b, SIlt. 2; 6.2-56, Shts.
2, 6, 7, 8, 9, 10, ll, 14, 24a Figure 6.2-88 SS SS, TS Update containment spray system description.
Revise spray flows from 7450 to 6880 gpm/loop (dry-well) and 450 to 420 gpm/loop (suppression chamber);
revise figure references showing spray patterns (6.2-46a).
Revise spray system flow percentages from 95 to 94 percent (drywell header) aod 5
to 6 percent (wetwell header)
(6.2-46b).
Revise number of spray nozzles per loop and correct SPRACO nozzle number (T6.2-51).
Add note regarding spray rates (T6.2-52).
Revise spray patterns (F6.2-41 through 6.2-43) to show current approximate patterns.
Add the yard as a termination point for bypass leakage paths (p. 6.2-54).
Add additional bypass leakage paths consisting of instrument air and nitrogen supply lines (6.2-54a, T6.2-S5a, T6.2-SSb).
Delete discussion regarding process lines that have nitrogen seals that prevent bypass
- leakage, including the discussion for the instrument air system IAS (6.2-54b, 6.2-55a, 6.2-55b, T6.2-56, Sht.
- 24a, F6.2-88).
Clarify that no credit is taken for a water seal in the feedwater system piping (6.2-54b).
Delete Note 30 from penetrations 48, 23, 39, 40, 43, 45, 53A, 538, Amendment 27 1020-12177-HC3 SIC-21 July 1986
i
~Pa es Pages 6.3-10a, 6.3-11 Figure 6.3-1 Figure 6A.1-3 Pages 6A.2-7, 6A.2-14 Table 6A.2-la Figure 6A.2-13 Page 6A.3-21 Pages 5A.4-22, 6A.4-23 Table 6A.4-10, Sh.
2 Figure 6A.4-48 Pages 6A.9-4, 6A.9-5, 6A.9-6 Tables 6A.9-2a, 6A.9-2b Change Code SS SS Descri tion
- 53C, 91A, and 918 since these lines are considered as bypass leakage
- paths, and change "NO" to "YES" for penetration 32 (T6.2-56, Shts.
2, 6, 7, 8, 9, 10, 11, 14).
The restricting orifice in the HPCS discharge line from the pump to the injection valve has been deleted.
The orifice has been determined to be not necessary to limit flow below the pump runout limit.
Updated to reflect recent analyses performed for the downcomers, and to incorporate editorial correc-tions.
Add pedestal to Fig. 6A.1-3.
Revise table number (6A.2-7).
Add references 9 and 10 (6A.2-14).
Delete redundant load combination (T6A.2-la, Sht.
1).
Add clarifying note (1) (Table 6A.2-la, Sht. 2).
Revise note 1 regarding time dur-ation and correct figure title (F6A.2-13).
Add equivalent occur-rence factor (EOF) of 3 '
for the downcomer evaluation and change 0.20 to 0.25 (6A.3-21, 6A.4-22, 6A,4-23).
Add footnote
- indicator to downcomer index numbers 65 and 117 (T6A.4-10, Sht. 2).
Figure 6A.4-48 revised to incorporate current analysis results.
Revise 123 to 121 downcomers (6A.9-4).
Revise 115 to 113 downcomers and delete mention of four truncated vacuum breaker downcomers not submerged in the pool (6A.9-5).
Add reference to Table 6A.9-2a and 6A.9-2b (6A.9-6).
Provide updated downcomer ASME Code Class 2 stress summary results (T6A ~ 9-2a).
Add table showing downcomer functional capability stress summary results (T6A.9-2b).
Amendment 27 1020-12177-HC3 S1C-22 July 1986
't
~Pa es Pages 7.6-2a, 7.7-5 Pages 8.1-2, 8.1-3 Figure 8.1-1 Page 8.3-24a Page 8.3-59 Page Q&R F430.24-2 Pages 9.1-31, 9.1-41, 9.1-42 Figure 9.1-7 Pages 12.5-7a, 12.5-9 Pages 9.2-10, 9.2-11, 9.2-12, 9.2-13, 9.2-16 Change Code SS SS SS, TS SS, TS SS Descri tion Delete statement regarding IEEE 279 applicability to high/low pressure interlocks.
Conformance with this standard is discussed in Section 7.6.2.2.
Delete reference to Section 7.2.1.2.2 for main steam line leak detection (p. 7.6-2a).
Clarify determination of APRM and RBM rod block settings.
Update description of the NMPC utility grid including the total circuit mileage, number of 115-kV and 345-kV lines, and interconnections to reflect the current grid system.
Clarify that for the HPCS diesel generator, a
LOCA signal would override the test start signal during the auto mode.
Correct equalizing charge value from 139.8 to 137.5 volts for Division III consistent with the response to Question F430.24 (8.3-59).
139.8 volts is correct for Divisions I and II.
Revise 137.4 to 137.5 volts dc in the response to Question F430.24.
Revise water shielding for active fuel in transit based on final fuel bundle dimensions and fuel grapple elevation.
Change 8 ft-6 in to 8 ft-1/2 in (pp 9.1-31, 12.5-7a, 12.5-9).
Change 7 ft to 6 ft-7 1/2 in (pp. 9.1-41, 9.1-42, F9.1-7).
Clarify that the double blade
- guide, though lifted 5 in higher than a fuel assembly, still will not exceed the energy of a dropped fuel assembly (p. 9.1-42).
Delete recirculation pump seal coolers from a list of components provided backup coding by the RBCLCH system (pp. 9.2-10, 9.2-12, 9.2-16).
Clarify that a
combination of any two main pumps, Amendment 27 1020-12177-HC3 SIC-23 July 1986
~Pa es Change Code Descri tion two booster
- pumps, and two,heat exchangers will provide maximum heat removal capacity, while maintaining a cooling water temperature of 89'F (instead of 95').
Delete "when service water temp.
is 77'F."
(p. 9.2-12)
Change locked to normally closed isolation valves (p. 9.2-13).
Page 9.5-6 SS Clarify actuation of Halon 1301 systems by adding that the main control room PGCC systems are actuated by thermal detection and the radwaste systems are actuated by smoke detection.
(Letter No.
NMP2L 0512 dated October 11, 1985.)
Pages 9.5-25, 9.5-25a SS Include discussion of fuel oil day tank vent capability in the event of a tornado.
Discuss the absence of flame arrestors on the vent
- lines, which is acceptable per API Standard No. 2000.
Pages 9.5-42, 9.5-43a, 9.5-43b, 9.5-51b Tables 11.2-3, 11.2-5, 11.2-6 SS SS Revise Division III diesel generator auxiliary system descriptions.
Change maximum starting air operating pressure from 250 to 240 psig.
An automatic separator, rather than a drain, removes condensate from the starting air (9.5-42).
Clarify that air start, system controls are located on a
panel near the compressor, and on the air dryer (9.5-43a).
Delete statement that air dryer is seismically qualified (9.5-43b).
Delete statement concerning maintaining diesel generator room temperature above 65'F (9.5-5lb).
Revise material and concentration balance for liquid waste system based on latest estimates (T11.2-3).
Revise design and expected annual liquid releases due to revised balance and change in release due to anticipated operational occurrences from 0.15 to 0.1 Cl/yr.
Amendment 27 1020-12177-HC3 SIC-24 July 1986
~Pa es Pages 11.4-3a, 11.4-5 Change Code SS Descri tion The solid radwaste backup facility will use containers sized up to 200 cu. ft.
Page 15.6-12a.l Table 15.6-13, Sh.
2, 9, 9a, 10 Tables
- 15. 6-15b,
- 15. 6-16b SS Incorporate revised radiological effects analysis results to incor-porate additional bypass leakage path contributi.ons.
Control room free air volume and intake rate values revised also.
(Letter No.
NHP2L 0761 dated June 30, 1986.)
Amendment 27 1020-12177-HC3 SIC-25 July 1986
0 0
r
NINE MILE POINT NUCLEAR STATION UNIT 2 NIAGARA MOHAWK POWER CORPORATION FSAR AMENDMENT RECEIPT ACKNOWLEDGEMENT I acknowledge receipt of:
Amendment 27 My copy has been
- updated, and superseded pages have been removed and destroyed.
Set Reassi nment and/or Set Holder Chan e of Address (if necessary)
Please reassign this manual to, and/or change my address as follows:
Please furnish all requested information and return to:
A. L. Monahan Stone 6 Webster Engineering Corporation 3 Executive Campus P.O.
Box 5200 Cherry Hill, NJ 08034 Name of set holder Set No.
Company Signature Date 2458-1217718-HC2
0
{'>&"
INSERTION INSTRUCTIONS The following instructions are for the insertion of the current amendment into the Nine Mile Point Unit 2 FSAR.
Remove
- pages, tables, and/or figures listed in the REMOVE column and re-place them with the
- pages, tables, and/or figures listed in the INSERT column.
Dashes
(---) in either column indicate no action required.
Vertical bars have been placed in the margins of inserted pages and ta-bles to indicate revision locations.
Amendment 27 2453-1217718-HC2 FII-1 July 1986
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Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 2 Remove T 1.8-1 (44 of 169)
T 1'-1 (119 of 169)
Insert T 1.8-1 (44 of 169)
T 1.8-1 (119 of 169)
A 1. 9-15 A '1. 9-37 A 1.9-42 A 1.9-42 A 1.9-61 A 1.9-61 A 1.9-61 A 1.9-61 A 1.9-78 (1 of 1)
(1/2 of 2)
(1/2 of 2)
(2 of 2)
(1 of 4)
(2 of 4)
(3 of 4)
(4 of 4)
(1 of 1)
A 1.9-15 (1 of 1)
A 1.9-37 (1/2 of 2)
A 1.9-42 (1/2 of 2)
A 1.9-61 (1/la of 4)
A 1.9-61 (lb/2 of 4)
A 1.9-61 (3/4 of 4)
A 1..9-78 (1 of 1) 1.10-64gb/64h 1.10-85h/86 1.10-91/92 1.10-95/96 1.10-101/102 1.12-11/12 1.12-37/38 1.10-64gb/64h 1.10-85h/86 1.10-91/92 1.10-95/96 1.10-101/102 1.12-11/12 1.12"37/38 Amendment 27 2453-1217718-HC2 FII-2 July 1986
Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 3 Remove 2.4-27/28, 2.5-167/167a 2.5"167b/167c 2.5-194a/194b Insert 2;4-27/28 2.5-167/167a 2.5-167b/167c 2.5-194a/194b Amendment 27 2453-1217718-HC2 July 1986
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INSERTION INSTRUCTIONS VOLUHE 4 Remove F 2.5-96E F 2 '-96F F 2.5-188 Insert F 2.5-96E F 2.5-96F F 2.5-188 Amendment 27 2453-1217718-HC2 July 1986
ine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 8 Remove 3-xli/xlil 3.1-33/34 3.1-47/48 Insert 3-xli/xlil 3.1-33/34 3.1-47/48 T 3.2-1 T 3.2-1 T 3.2-1 T 3.2-1 T 3.2"1 T 3.2-1 T 3.2"1 (3 of 26)
(9 of 26)
(14 of 26)
(15 of 26)
(15a of 26)
(16 of 26)
(26f of 26)
T 3.2-2 (1 of 1)
T 3.2"1 T 3.2-1 T 3.2-1 T 3.2-1 T 3.2-1 T 3.2-1 T 3.2-1 T 3.2-1 T 3.2-2 (3 of 26)
(9 of 26)
(14 of 26)
(15 of 26)
(15a of 26)
(16 of 26)
(26f of 26)
(26g of 26)
(1 and 2 of 2) 3.4-3/3a T 3.4-2 (1 of 3)
T 3.4-2 (3 of 3)
T 3.4-5 (1 and 2 of 2) 3.4-3/3a T 3.4-2 (1 of 3)
T 3.4-2 (3 of 3)
T 3.4-5 (1 and 2 of 2)
Amendment 27 2453-1217718-HC2 FII-5 July 1986
I
Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 9 Remove Insert 3.5-3/4 3.5-4a/4b 3.5-4c/4d 3.5-5/6 3.6A-5/6 3.6A-37/38 3.6A slip sheet 3.5-3/4 3.5-4a/4b 3.5-4c/4d 3.5-5/5a 3.5"5b/6 3.6A-5/6 3.6A-37/38 3.6A slip sheet Amendment 27 2453-1217718"HC2 FII-6 July 1986
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ine Mile Point Unit 2 FSAR Remove INSERTION INSTRUCTIONS VOLUME 10 Insert 3.6A slip sheet F 3.6A-52 F 3.6A-53 F 3.6A-54 F 3.6A-55 F 3 'A-56 F 3.6A-57 F 3.6A-58 F 3.6A-59 F 3.6A-60 3.6B-9/9a T 3.6B-2 3.7A-7/7a 3.7A-31/32 3.8-37/38 3.8-75/76 T 3.8-5 (1 and 2 of 2)
T 3.8-6 (1 and 2 of 2)
T 3.8-7 (1 and 2 of 2)
T 3.8-15 (1 of 2) 3.6A slip sheet F 3.6A-50 F 3.6A-51 F 3.6A-52 F 3.6A-53 F 3.6A-54 F 3.6A-55 F 3.6A-56 F 3.6A-57 F 3.6A-58 F 3.6A-59 F 3.6A-60 3.6B>>9/9a T 3.6B"2 3.7A-7/7a 3.7A-31/32 3.8-37/38 3.8-75/76 T 3.8-5 (1 and 2 of 2)
T 3.8-6 (1 and 2 of 2)
T 3.8-7 (1 and 2 of 2)
T 3.8-15 (1 of 2)
Amendment 27 2453-1217718-HC2 FII-7 July 1986
Nine Mile Point Unit 2 FSAR Remove 3.9A-9/9a 3.9A-11/12 3.9A-15/16 3.9A-21/21a 3.9A-26a/26b T 3.9A-4 (1 of 6)
T 3.9A-4 (2 of 6)
T 3.9A-4 (3 of 6)
T 3.9A-4 (5 of 6)
T 3.9A-4 (6 of 6)
T 3.9A-5 (2 of 3) 3.9B-15/16 T 3.9B-2s (2 of 2)
INSERTION INSTRUCTIONS VOLUME ll Insert 3.9A-9/9a 3.9A-ll/lla 3.9A"lib/12 3.9A-15/16 3.9A-21/2la 3.9A-26a/26b T 3.9A-4 (1 of 6)
T 3.9A-4 (2 of 6)
T 3.9A-4 (3 of 6)
T 3.9A<<4 (5 of 6)
T 3.9A-4 (6 of 6)
T 3.9A-4 (6a of 6)
T 3.9A-4 (6b of 6)
T 3.9A-5 (2 of 3) 3.9B"15/16 3.9B-16a/16b T 3.9B-2s (2 of 2)
Amendment 27 2453-1217718-HC2 FII-8 July 1986
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Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 12 Remove Insert 3.10A-5/-
3A-i/ii 3A-v/vi 3A-vii/viii 3A-ix/x 3A.9-1/2 3A.9-3/4 3A.9"5/6 3A.10-1/2 3A.10"3/-
F 3A.12-1 F 3A.22-1 3C-5/6 3C-ll/lla 3C-lib/12 3C-23/24 3C"25/26 3C-27/28 3C-29/30 3C-31/32 3C"33/34 T 3C.4-1 T 3C.4-2 T 3C.4-3 T 3C.4-4 T 3C.5-1 4.1-5/6 4.5-3/4 4.5-5/6 4.5-7/8 4.6-3/4 3.10A-5/"
3A-i/ii 3A-v/vi 3A-vii/viii 3A-ix/x 3A.9-1/2 3A.9-3/4 3A.9-5/6 3A.10-1/2 3A.10-3/-
T 3A.10-1 F 3A.10-4 F 3A.12-1 F 3A.22-1 3C-5/6 3C-ll/lla 3C-lib/12 3C-23/24 3C-25/26 3C-26a/26b 3C-27/27a 3C-27b/28 3C-29/30 3C-30a/30b 3C-31/32 3C"33/34 T 3C.4-1 T 3C.4-2 T 3C.4-3 T 3C.4-4 T 3C.5"1 4.1-5/6 4.5-3/4 4.5-5/6 4.5-7/8 4.6-3/4 Amendment 27 2453"1217718-HC2 FII-9 July 1986
7 e
ine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 13 Remove F 5.1-2 (1 through 3 of 3)
- 5. 3-5/6 5.3-7/7a 5.3-21/22 5.4-27/28 5.4-41/42 6-xa/xb 6-xv/xvi 6-xvii/xviii 6-xix/xixa 6-xixb/xx 6.1-1/2 T 6.1"1 (1 of 2)
T 6.1-3 Insert F 5.1-2 (1 through 3 of 3) 5.3-5/6 5.3-7/7a 5.3-21/22 5.4-27/28 5.4-41/42 6-xa/xb 6-xv/xvi 6-xvii/xviii 6-xix/xixa 6-xixb/xx 6.1-1/2 T 6.1-1 (1 of 2)
T 6.1-3 Amendment 27 2453-1217718-HC2 FII-10 July 1986
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Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 14 Remove 6.2-46a/46b 6.2-49/50 6.2-51/51a 6.2-51b/52 6.2-53/53a 6.2-53b/54 6.2-54a/54b 6.2-55/55a 6.2-55b/55c 6 '-57/57a 6.2-73/74 6.2-75/75a 6.2-77/77a 6.2-83/83a 6.2-83b/84 6.2-85/85a 6.2-85b/86 6.2-87b/88 T 6.2-3 (1 and 2 of 2)
T 6.2-37 T 6.2-51 T 6.2-52 T 6.2-55a (2 of 2)
T 6.2-55b (2 of 2)
T 6.2-56 (2 of 24)
T 6.2-56 (6 of 24)
T 6.2-56 (7 of 24)
T 6.2-56 (8 of 24)
T 6.2-56 (9 of 24)
T 6.2-56 (10 of 24)
T 6.2-56 (11 of 24)
T 6.2-56 (14 of 24)
T 6.2-56 (22 of 24)
T 6.2-56 (24a of 24)
-T 6.2-57 T 6.2-60 T 6.2-61 F 6.2-10 F 6.2-40 F 6.2-41 F 6.2-42 F 6.2-43 F 6.2-50 F 6.2-68a F 6.2-69 Insert 6.2-46a/46b 6.2-49/50 6.2-51/5la 6.2-51b/52 6.2-53/53a 6.2-53b/54 6.2-54a/54b 6.2-55/55a 6.2-55b/55c 6.2-57/57a 6.2-73/74 6.2-75/75a 6.2-77/77a 6.2-83/83a 6.2-83b/84 6.2-85/85a 6.2-85b/86 6.2-87b/88 T 6.2-3 (1 and 2 of T 6.2-37 T 6.2-51 T 6.2-52 T 6.2-55a (2 and 2a T 6.2-55b (2 and 2a T 6.2-56 (2 of 24)
T 6.2-56 (6 of 24)
T 6 '-56 (7 of 24)
T 6.2-56 (8 of 24)
T 6.2-56 (9 of 24)
T 6.2-56 (10 of 24)
T 6.2-56 (11 of 24)
T 6.2-56 (14 of 24)
T 6.2-56 (22 of 24)
T 6.2-56 (24a of 24 T 6.2-57 T 6.2-60 T 6.2-61 F 6.2-10 F 6.2-40 F 6.2-41 F 6.2-42 F 6.2-43 F 6.2-50 F 6.2-68a F 6.2<<69 2) of 2) of 2)
Amendment 27 2453-1217718-HC2 FII-11 July 1986
Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 14 (Cont)
Remove F 6.2-70 (10 of 43)
F 6.2-70 (16 of 43)
F 6.2-70 (17 of 43)
F 6.2-70 (22 of 43)
F 6.2-71A F 6.2-71B F 6.2-88 Insert F 6.2-70 (10 of 43)
F 6.2-70 (16 of 43)
F 6.2-70 (17 of 43)
F 6.2-70 (22 of 43)
F 6.2-71A F 6.2-71B 6.2-88 F 6.2-89 F 6.2-90 Amendment 27 2453-1217718-HC2 FII-12 July 1986
ine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 15 Remove 6.3-10a/10b 6.3-11/12 6.3-15/16 6.3-31/32 F 6.3-1 (1 of 2)
T 7.1-2 (1 of 3)
T 7.1"2 (3 of 3) 7.2-21/-
7.3"5/6 7.3-19b/20 7.3-33/34 Insert 6.3-10a/10b, 6.3-11/12 6 '-15/16 6.3-31/32 F 6.3-1 (1 of 2)
T 7.1-2 (1 of 3)
T 7.1-2 (3 of 3) 7.2-21/-
7.3-5/6.
7.3-19b/20 7.3-33/34 Amendment 27 2453-1217718-HC2 FII-13 July 1986
k 0
Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOIUME 16 Remove Insert 7.4-3/4 T 7.4-1 7.5-1/2 7.5"5/6 T 7.5-1 (1 of 14) 7.6-2a/2b 7.6-3b/4 7.6-7/8 7.6-17/18 7.6"19/20 7.6-21/22 T 7.6-1 T 7.6-3 (2 of 2)
T 7.6-5 T 7.6-6 F 7.6-7 F 7.6-8 7.7-5/6 7.7-7/8 7.7-13/14 7.7-22a/22b 7.7-23/24 8.1-1/2 8.1-3/4 F 8.1-1 8.3-13/14 8.3-24a/24b 8.3-39/40 8.3-59/60 7.4-3/4 T 7.4-1 7.5-1/2 7.5-5/6 T 7.5-1 (1 of 14) 7.6-2a/2b 7.6-3b/4 7.6-7/8 7.6-17/18 7.6-19/20 7.6-21/22 T 7.6-1 T 7.6-3 (2 of 2)
T 7.6-5 T 7.6-6 F 7.6-7 F 7.6-8 7.7-5/6 7.7-7/8 7.7-13/14 7.7-22a/22b 7.7-23/24 8.1-1/2 8.1-3/3a 8.1-3b/4 F 8.1-1 8.3-13/14 8.3-24a/24b 8.3-39/40 8.3-59/60 Amendment 27 2453-1217718"HC2 FII-14 July 1986
Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 17 Remove Insert T 8.3-3 (2 of 2)
T 8.3-3A T 8.3-4 (3 of 60)
F 8.3-3 (2 of 2) 9.1-31/32 9.1-41/42 F 9.1-7 T 8.3-3 (2 of 2)
T 8.3-3A T 8.3-4 (3 of 60)
F 8.3-3 (2 of 2) 9.1-31/32 9.1-41/42 F 9.1-7 Amendment 27 2453-1217718-HC2 FII-15 July 1986
0 P
Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 18 Remove 9.2-9/10 9.2-11/lla 9.2-11b/12 9.2-13/14 9.2-15/16 Insert 9.2-9/10 9.2-11/lla 9.2-11b/12 9.2-13/14 9.2-15/16 Amendment 27 2453-1217718-HC2 FII-16 July 1986
.S
/
ine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 19 Remove 9.3-3/4 9.3-7/8 9.3-23/23a 9.3-23b/24 9.3-25/26 9.3-26a/26b 9.3-27/28 9.3-31/32 F 9.3-13 (1 of 10)
F 9.3-14 (1 of 3)
F 9.3-14 (3 of 3)
F 9.3-15 F 9.3-16 (6 of 7)
Insert 9.3-3/4 9.3-7/8 9.3-23/23a 9.3-23b/24 9.3-25/26 9.3-26a/26b 9.3-27/28, 9.3-31/32 F 9.3-13 (1 of 10)
F 9.3-14 (1 of 3)
F 9.3-14 (3 of 3)
F 9.3-15 F 9.3-16 (6 of 7)
Amendment 27 2453"1217718-HC2 FII-17 July 1986
INSERT10N INSTRUCTIONS VOLUME 21 Remove 9.5-5/6 9.5-6a/6b 9.5-25/25a 9.5-25b/26 9.5-41b/42 9.5-43/43a 9.5-43b/44 9.5-51b/52 9.5-65/66 Insert 9.5"5/6 9.5-6a/6b 9.5-25/25a 9.5-25b/26 9.5-4lb/42 9.5-43/43a 9.5-43b/44 9 '-51b/52 9.5-65/66 T 9.5-3 (9a of ll)
Amendment 27 2453"1217718-HC2 FII-18 July 1986
Nine Nile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOIlME 23 Remove Insert 9A.3-15/16 9A.3-17b/18 9A.3-31/31a 9A.3-51b/52 F 10.1-4a through 4d F 10.1-7a through 7w 10 '-3/3a 9A.3-15/16 9A.3-17b/18 9A.3-31/31a 9A.3-51b/52 F 10.1-4a through 4d F 10.1-7a through 7w 10.2-3/3a Amendment 27 2453-1217718-HC2 FII-19 July 1986
r~
i
INSERTION INSTRUCTIONS VOLUME 24 Remove 10.3-1b/2 10.4-9/10 10.4-17/18 10.4-27/28 T 10.4-2 Insert 10.3"1b/2 10.4-9/10 10.4-17/18 10.4-27/28 T 10.4-2 T 11.2"1 (2 of 5)
T 11.2-3 T 11.2-5 (1 and 2 of 2)
T 11.2-6 (1 and 2 of 2)
T 11.2-1 (2 of 5)
T 11.2-3 T 11 '-5 (1 and 2 of 2)
T 11.2-6 (1 and 2 of 2)
Amendment 27 2453-1217718-HC2 FII-20 July 1986
Nine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 25 Remove Insert 11.4-3/3a 11.4-3b/4 11.4-5/6 F 11.4-la thr'ough lh T 12.3-4 (1 through 4 of 4) 11.4-3/3a 11.4"3b/4 11.4-5/6 F 11.4-1a through 1h T 12.3-4 (1 through 4 of 4)
Amendment 27 2453-1217718-HC2 FII-21 July 1986
INSERTION INSTRUCTIONS VOLUME 26 Remove Insert 12.5-7/7a 12.5-9/10 12.5-7/7a 12.5-9/10 Amendment 27 2453-1217718-HC2 FII-22 July 1986
ine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS VOLUME 27 Remove Insert 15.1-3/4 15.1-7/8 15.1-11/12 T 15.2-12 15.3-7/8
- 15. 4-15b/16 T 15.4-8 15.1-3/4 15.1-7/8 15.1-11/12 T 15.2-12 15.3-7/8 15.4-15b/16 T 15.4-8 15.6-12a/12a.l T 15.6-13 (2 of 11)
T 15.6-13 (9 of ll)
T 15.6<<13 (10 of ll)
T 15.6-15b T 15.6-16b 15.6-12a/12a.l T 15.6-13 (2 of ll)
T 15.6-13 (9 of ll)
T 15.6-13 (9a of 11)
T 15.6-13 (10 of 11)
T 15.6"15b T 15.6-16b Amendment 27 2453-1217718"HC2 FII-23 July 1986
r 0!
ine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS QUESTIONS AND'ESPONSES VOLUME 1 Remove Insert QSR F210.38-1/2 QSR F251.1-1/2 QSR F210.38-1/2 Q&R F251.1-1/2 Amendment 27 2453-1217718-HC2 FII-24 July 1986
7
INSERTION INSTRUCTIONS QUESTIONS AND'ESPONSES VOLUME 2 Remove Q&R F280.23-1/-
SSC-5/6 Q&R F421.13-1/2 Q&R F421.13-5/6 Q&R F421.20-1/2 Q&R F421.23-1/2 Q&R F421.23-3/-
T 421.36-1 (1 of 18)
T 421.36-1 (2 of 18)
T 421.36-1 (14 of 18)
Q&R F430.24-1/2 Q&R F430.36-1/2 Q&R F430.44'-1/-
Q&R F430.49-1/-
Q&R F430.71"1/-
Insert Q&R F280.23-1/-
SSC-5/6 Q&R F421.13-1/2 Q&R F421.13-5/6 Q&R F421.20"1/2 Q&R F421;23-1/2 Q&R F421.23"3/".
T 421.36-,1 (1 of 18)
T'421.36-1 (2 of 18)
T 421.36-1 (14 of 18)
Q&R F430.24-1/2 Q&R F430.36-1/2
~ Q&R F430. 44-1/-
Q&R F430.49-1/-
Q&R F430.71-1/-
Amendment 27 2453-1217718-HC2 FII-25 July 1986
INSERTION INSTRUCTIONS QUESTIONS AND RESPONSES VOLUME 3 Remove Q&R F492.7-1/2 Q&R F620.1-1/-
Q&R F620.01-1/2 Q&R F620.05-1/"
Q&R F640.34-3/4 Insert Q&R F492.7-1/2 Q&R F620.1"1/-
Q&R F620.01-1/2 Q&R F620.05-1/-
Q&R F640.34-3/4 Amendment 27 2453-1217718-HC2 FII-26 July 1986
ine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS DESIGN ASSESSMENT REPORT APPENDIX 6A Remove 6A-viib/viii 6A-ixb/x 6A-xiii/xiv F 6A.1-3 6A.2-7/8 6A.2-13/14 T 6A.2-la (1 and 2 of 2)
F 6A.2-13 6A.4-21/22 6A.4-23/24 T 6A.4-10 (2 of 3)
F 6A.4-48 6A.9-3/4 6A.9-5/6 Insert 6A-viib/viii 6A-ixb/x 6A-xiii/xiv F 6A.1-3 6A.2-7/8 6A.2-13/14 T 6A.2-1a (1 and 2 of 2)
F 6A.2-13 6A.4-21/22 6A.4-23/24 T 6A.4-10 (2 of 3)
F 6A.4-48 6A.9-3/4 6A.9-5/6 T 6A.9-2a T 6A.9-2b T 6A.10-2 (1 of 2)
T 6A.10-2 (1 of 2)
Amendment 27 2453-1217718"HC2 FII-27 July 1986
ine Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS SAFE SHUTDOWN ANALYSIS APPENDIX 9B Remove T 9B.8-1 (66 of 75)
T 9B.8-1 (75 of 75)
Insert T 9B.8-1 (66 of 75)
T 9B.8-1 (75 of 75)
T 9B.8-1 (75a of 75)
Amendment 27 2453-1217718-HC2 FII-28 July 1986
e
4 1
e Mile Point Unit 2 FSAR INSERTION INSTRUCTIONS LIST OF EFFECTIVE PAGES Remove Insert EP-i EP l-l through 1-8 EP 2-1 through 2-20 EP 3-1 through 3-12 EP 4-1 and 4-2 EP 5-1 through 5-3 EP 6-1 through 6-6 EP 7-1 through 7-4 EP 8-1 through 8-3 EP 9-1 through 9-11 EP 10-1 and 10-2 EP ll-l and 11-2 EP 12-1 through 12-3 EP 15-1 through 15-5 Q&R-1 through QSR-14 DAR-1 through DAR-8 SSA-1 and SSA-2 EP-i EP l-l through 1"8 EP 2-1 through 2-20 EP 3-1 through 3-12 EP 4-1 and 4-2 EP 5-1 through 5-3 EP 6-1 through 6-6 EP 7-1 through 7-4 EP 8-1 through 8-3 EP 9-1 through 9-11 EP 10-1 and 10-2 EP 11 and 11-2 EP 12-1 through 12-3 EP 15-1 through 15-5 QSR-1 through Q&R-14 DAR-1 through DAR-8 SSA-1 and SSA-2 Amendment 27 2453-1217718-HC2 FII-29 July 1986
0
I 7 NIAGARA MOHAWK
~y NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 July 24, 1986 (NMP2L 0793)
Mr. Robert Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Bernero:
Re:
Amendment 27 to Application to Operating License Nine Mile Point Unit 2 Docket No. 50-410 In accordance with 10 CFR 50.30(c)(l) and your March 29, 1983 letter, enclosed are three originals and 60 copies of Amendment 27 to the Final Safety Analysis Report.
These changes incorporate certain responses into the text of the Final Safety Analysis Report.
Also included are changes that have resulted from our continuing review of these documents.
In the original submittal of the Final Safety Analysis Report on January 25, 1983, we requested proprietary status for certain figures in Section 6A in accordance with 10CFR2.790.
The September 21, 1983 letter from A. Schwencer to G. K. Rhode approved this proprietary status.
Amendment 27 contains updates to a figure in Section 6A.
Also enclosed is the Summary of Incorporated Changes.
This list is to assist the Nuclear Regulatory Commission in reviewing Amendment 27.
Very truly yours, C. V. Mangan Senior Vice President JM:ja 1853G Enclosures xc:
W. A. Cook, NRC Resident Inspector Project File (2)
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