ML20137D094
Text
h Publ c Serece Electnc and Gas g.
g Company 80 Park Plaza, Newark, NJ 07101/ 201430 8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Rerfilation November 25, 1985 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing Gentlemen:
FINAL SAFETY ANALYSIS REPORT, AMENDMENT 13 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric & Gas Company hereby files Amend-ment 13 to the Hope Creek Generating Station Final Safety Analysis Report (FSAR).
Pursuant to 10CFR50.30(c)(1)(i) and 10CFR51.40(b) this filing consists of sixty (60) copies of FSAR Amendment 13.
In accordance with 10CFR2.101( a) (4) and 10CFR50.30(c)(1), three (3) signed original af fidavits are enclosed.
Amendment 13 to the HCGS FSAR contains:
- 1) text changes due to the resolution of various Safety Evaluation Report (SER) open and confirmatory items includ ing the elimination of arbitrary intermediate pipe breaks, the revision to the radiation monitoring system, and the reorganization of the Nuclear Department; 2) updated drawings tabulated in FSAR Section 1.7; 3) specific information to address various Independent Design Verification Program Observation Reports;
- 4) revisions to maintain FSAR consistency with the Technical Specifications; and 5) general changes to the FSAR text, tables, and figures.
A brief summary and explanation for each change is provided in the attachment to this letter.
FSAR revisions, which affect SER Sections, have been noted with an asterisk in the attachment.
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fSe The Energy People QSc T3 TD b e n m.wo
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11/25/85 Reactor Regulation Should you have any questions on the subject filing, do not hesitate to contact us.
Very truly yours, lII'/
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Attachment C
D.
H. Wagner USNRC Licensing Project Manager A.
R.
Blough USNRC Senior Resident Inspector AM3 1/2
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-354 PUBLIC SERVICE ELECTRIC AND GAS COMPANY FINAL SAFETY ANALYSIS REPORT AMENDMENT 13 Public Service Electric & Gas Company (PSE&G) hereby submits Amendment 13 to the Hope Creek Generating Station (HCGS)
Final Safety Analysis Report (FSAR).
The HCGS FSAR amend-ment consists of text changes due to resolution of various Safety Evaluation Report (SER) open and confirmatory items, updated drawings tabulated in FSAR Section 1.7, specific information to address various Independent Design Verification Program (IDVP) Observation Reports (ors), revisions to main-tain FSAR consistency with the Technical Specifications, and general revisions to the FSAR text, tables and figures.
The matters set forth in this amendment are true to the best of my knowledge, information, and belief.
Respectively submitted, Public Service Electric and Gas Company By:
agh A
/ Th'o' mas
. ' Ma'rti6
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Vice P esident -
Engin ering and Construction Sworn to and subscribed before me, a Notary Public of New Jersey, this ff74 day of November 1985.
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mVID K. BURD un m AfiUC OF NEW JERSEY 4 sum. boires 10 23 90
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Page 1 of 13 4
ATTACHMENT AMENDMENT 13 TO THE HCGS FSAR DESCRIPTION OF REVISIONS BY FSAR SECTION i
l 1.8.1.29 A compliance statement regarding Regulatory 1
T1.ll Guide 1.29, Position C l.b has been added, and is compared to SRP Section 3.2.1, respectively.
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'l.8.1.52,~1.8.1.140
.These revisions reflect the ANSI standard T6.8-6, T9.4-6 to which the HVAC system will be tested.
i 1.8.1.68.3, These revisions reflect the fact that 14.2.12.1.27, Regulatory Guide 1.68.does not apply 14.2.13.4 to the Instrument Air Preoperational Test
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i regarding maximum particle size but in-stead ANSI MCll.1-1975 applies.
1.8.1.97 The deletion of the references to the Boiling Water Reactor Owners Group (BWROG) i position on Regulatory Guide 1.97 reflects the withdrawl on the BWROG position state-ment itself.
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l 1.10.2(I.B.1.2;
- These revisions detail the recent reorgani-I.C.5; II.K.3.17),
zation of the Nuclear Department and 12.5, 13.1, 13.2, provides information necessary to close 13.4, 13.5, 17.2 SER Open Item ll.
1 1.10.2 (III.A.1.2)
This revision provides the current condition j
of the Emergency Operations Facility.
T1.11-1, T3.10-1,
- Various revisions are being made to relect T3.ll-5, 5.2.5.1.1, the design of the Radiation Monitoring 5.2.5.1.2, T7.1-1, System (RMS).
Functionally, the RMS 4
7.3.1.1.2, 7.3.1.1.7, has not changed; however, the RMS supplier 7.3.1.1.9, 7.3.1.1.10, has changed.
This change affects various T8.3-1, 11.5.1.1.1, SER sections.
11.5.1.1.2, 11.5.2 i
11.5.2.1.2-11.5.2.1.5, 11.5.2.2.1-11.5.2.2.20, Tll.5-1, 2,
3, T12.3-9, 12.3.4.1.1-12.3.4.1.6, F12.3-59 L
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'l.14..l.19.2 This revision reflects the Inservice Inspection Program commitment to the ASME Section XI Code, Winter 1980 Edition, i
which requires quarterly testing.
2.5.4.10.3 An additional paragraph is included to provide a cross-reference to the inde-pendent stability analysis for the intake structure and power block.
This revision j
provides the PSE&G response to IDVP OR 198.
5 T3.2-3, These additions address various standards 5.2.1.3.2.2, and code cases being utilized during T5.2-2 the As-Built Reconciliation (ABR) program.
a F3.5-26,
- These revisions incorporate the standby 9.5.8.3 diesel generator exhaust stack roof exten-9.5.8.6 sion which prevents thermal degradation of the roof concrete from exhaust gas impingement.
This revision impacts SER Section 9.5.8.
3.6.2.1.1.3,
- Various deletions regarding arbitrary 3.6.2.1.1.4, 3.6.2.7.1, intermediate pipe break locations, and T3.6-3, 9,
11-15, 17, associated whip restraints or shim pacs, 20-23, F3.6-3, 14, 16, on Class 1, 2 and 3 piping inside and r
18, 19, 22, 23, 27, outside of containment where such breaks
'30-33 were chosen strictly to meet the minimum break location criteria.
These revisions i
have been deemed acceptable to the NRC staff in a letter from Mr. W.R.
Butler i
(NRC) to Mr.
R.L.
Mittl (PSE&G) dated September 20, 1985 but requires revision of SER Section 3.6.2.
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3.6.2.1.1.4 This revision reflects the correct criteria for postulating breaks in Class 2 and i
3 piping, i.e.,
SRP 3.6 does not require l
calculation of the cummulative usage j
factor.
3.6.2.2 An addition is provided to clarify which methods were utilized in analyzing pipe response to pipe break loads.
This revision provides the PSE&G response to IDVP OR 198 (Item 2d).
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'3.7.3.16 This revision is provided to update and elaborate on the justification for the ten (10) cycle fatigue calculations used in determining the most limiting RPV component in the BWR/4 product line.
T3.8-3 The table has been revised to reflect a change in allowable stress values for a specific load combination, as well as various editiorial changes.
3.9.1.2.5 Additional sections are provided since SRP 3.9 requires that all computer pro-grams used in the design of mechanical components be identified and described in the FSAR.
Program NE452 is deleted because the RHR Steam Condensing Mode will not be utilized.
This revision provides the PSE&G response to IDVP OR 194.
3.9.2.4.2
- Additional discussion is provided to close out DSER Open Item 103 and provide the PSE&G response to IDVP OR 89.
3.9.3.2.3,
- These revisions identify ECCS motor quali-3.10.4.2 fication information recently made available and provides information necessary to close SER Open Item 2.
3.9.3.2.7.3 An additional section is provided which addresses ANSI Standards N41.6 and B16.41-1983, as well as draft ANSI /ASME Standards QP-1, 2,
3 and 4, for the quali-fication of valves, pumps and motors.
This information was previously provided to the staff in letter from Mr.
R.L.
Mitti IPSE&G) to Mr. W.R.
Butler (NRC) on September 18, 1985 and provides information necessary to close SER Open Item 2b(5).
T3.9-5v Additions are made to define the variables Fo and Mo.
This revision provides the PSE&G response to IDVP OR 25.
T3.9-9, 13 Revisions reflect the use of later editions of ASME Section III code for Class 1 piping stress analysis and CRD piping design.
The use of these later code editions result in more accurate results.
Page 4 of 13 T3.10-3, 4 These revisions re-format the seismic qualification results for Category I Electrical and Instrument Equipment and Class lE Control Panels, Local Panels and Racks in tabular form similar to that of the River Bend Station.
These revisions provide the PSE&G response to IDVP ors 138 and 139.
T3.ll-5, These updates identify components included T3.11-6 in the Electrical Environmental Qualification Program.
These revisions provides infor-mation necessary to close SER Open Item 2.
4.3.2.1 Editorial cross-reference corrections T4.4-13 This clarification is provided to correctly address the results of the natural circulation stability analysis.
T5.2-2 These additions are made to include ASME Code Case Application 27 - Code Cases 1573, 1635-1 and N-199.
5.4.7.1.1.2 This revision is necessary to delete the analytical values associated with the LPCI mode injection signals and replace them with a cross reference to the Technical Specifications, thereby eliminating the potential for conflict or misinterpretation.
5.4.8.2 This revision provides the correct termin-ology and verification process for resin size and capacity of the filter-deminer-alizer resins.
T6.1-4 This table was revised to reflect the as-built condition of the drywell coatings and various specification changes.
6.2.3.2.3, 9.3.2.1.2, These revisions detail changes in the 9.3.2.2.2, T9.3-3 relocation of PASS equipment and various modifications to that equipment to reflect as-built conditions.
6.2.5.2.4 This revision reflects specification changes.
T6.2-16, 24, These revised descriptions of the primary F6.2-28 containment isolation fnatures reflect the as-built configuration (spare instrument lines) and recently available information (probe guide tube and TIP purge system).
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'T6.2-30 This revision shows which electrical pene-trations are based on electrical drawings rather than civil drawings.
6.3.2.2.1 This revision clarifies the power supply for CST level instrumentation and suction piping heat tracings.
This revision re-flects the as-built configuration and NRC Bulletin 79-24.
T6.3-3, Revised Notes 3 and 4, respectively, T6.3-5 indicate a 12*F not 12 C increase in PCT and a correct reference to peak clad oxidation fractions.
This information is related to SER Confirmatory Items 14 and 24.
F6.3-14 This revision identifies the DC source failure channel.
6.8.1.2, The deletions of the incorrect discussion 6.8.2.2 of the operational mode of the charcoal filter manual deluge fire suppression system is in favor of the correct discus-sion in the referenced sections given.
T6.8-6 This revision of the test frequency for sucessive canniters of charcoal in the airstream of the charcoal adsorbers, from 12 to 18 months, reflects the requirements of Regulatory Guide 1.52 and the Technical Specifications.
7.1.2.4, 7.1.2.6, These revisions are necessary for the 7.2.1.3, 7.3.1.2, FSAR to match the Technical Specifications.
7.4.1.6, 7.6.1.9 7.2.1.1 This revision clarifies the fact that a 10-second delay for resetting the RPS trip actuator logic is not applicabic if a scram has not occurred, i.e. a trip of.one or two unrelated trip actuators.
7.3.1.1.11.2 The deletion of the reference to the " process hampling shutof f valves" in the Saf ety Auxiliaries cooling System is necessary since they were replaced with grab valves.
This revision provides the PSE&G response to IDVP OR 150.
T7.4-2 This addition is provided to clarify l
the operation of SACS valve IIV2520B on l
RSP takeover.
This valve will open auto-matically on RSP takover even though no control is involved because when power is removed from the solenoid on takeover the valve fails open.
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Revisions in this table also indicate l
that SACS valves HV-2522B and HV-2496B, as well as HV-2522D and HV-2496D, share l
a common control switch / indication at the remote shutdown panel.
T7.4-3 An editorial revision is made to show l
that the Class lE channel for the locally operated safety / relief valves (SRVs) in the Nuclear Boiler System is the "D" channel not the "A"
channel.
T7.5-1 This change reflects the addition of contain-ment isolation valves identified at the July 19, 1984 meeting between PSE&G and the Containment Systems Branch (CSB) of the Nuclear Regulatory Commission (NRC).
7.6.1.4.2 This addition identifies non-RPS inter-l f acing cables or wires as being wrapped in SIL-temperature tape if the separation criteria of Regulatory Guide 1.75 was not conformed to.
7.6.1.6.2, Additional test is provided to clarify 7.4.1.2.2 the Main Steam Safety / Relief Valve low-low set logic operation and corrections are made to provide accurate cross-references.
l 8.1.3.9.2 An addition is made to address the MAAC criteria.
I 8.1.4.8 HCGS conformance to Regulatory Guide 1.41 is added.
8.1.4.14.1.3 This revision reflects the actual installation l
of a non-Class lE cable feeding a non-Class 1E load from a Class lE breaker which, rather than routing in a conduit, is instead wrapped with Siltemp material.
This revision reflects the PSE&G resolution of IDVP OR 181.
8.1.4.14.1.3, These revisions indicate that associated 8.1.4.14.2 circuits are identified as Class lE circuits and that the identification requirements for associated channels and cables have been deleted.
No unique and distinctive identification of associated cables and raceways have been considered necessary as such items are treated and identified as Class lE during their design and installation.
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'8.2.1.1 Clarification of the transmission system design details is provided.
8.2.1.3 This revision correctly addresses safety features for the operation of the trans-former diconnect control switch.
8.2.1.4 This revision is to correctly indicate compressor motor feeds as well as clarifying other switchyard design details.
This section is also revised to correctly address the grounding and current transformer fault detection design details.
8.2.1.5 This revision is necessary to correctly identif y ground switches which are utilized in the monitoring of the offsite power sources.
8.2.1.5.1 This revision is to clarify switchyard relay room distribution panels.
8.3.1.1 This revision is to provide correct section cross-references.
8.3.1.1.1 These additions are made to address the non-Class lE transformer impedance values.
8.3.1.1.2.6 This change revises the Class lE equipment impedence values for transformers, interrupting ratings of circuit breakers and clarifies the capability of the 480-V MCC buses to withstand short-circuits.
These revisions provide the PSE&G response to IDVP ors 21 and 22.
8.3.1.1.2.7 This change clarifies the load shedding feature for non-Class lE loads connected to Class lE unit substation buses.
This revision reflects the PSE&G response to IDVP OR 212.
8.3.1.2.1
- Various additions are made to describe the protective features for the offsite buses within the diesel generator rooms against a fire and reference the safe shutdown analysis performed.
A revised statement on separation between onsite and offsite power is made.
These changes are required as a result of the April 25, 1985 meeting betwoon PSE&G and the NRC on the diesel generator and bus duct configuration.
This change affects SER Sections 8.2.2.3 and 8.2.2.4.
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Page 8 of 13 8.3.1.2.1, These changes reflect revised editorial T8.3-ll, 15 code case references, voltage changes based on revised electrical calculations and a change to the 4.16-0.48kV transformer tap.
These revisions provide the PSE&G response to IDVP OR 215.
8.3.2.1.2.3 This revision is provided to accurately detail the Class lE battery charger charging capacity capability.
This revision re-flects the PSE&G response to IDVP OR 41.
T8.3-1, 2,
3, 4,
5, 6
The revised diesel generator loading tables incorporate as-built HVAC loading require-monts and the latest assignment of loads among the diesels.
In addition, Item 41, Standby Liquid Control Pumps, is not a sequenced load but is a connected load at 13 seconds.
Additional miscellaneous loads are revised and total demand kWs and adjusted accordingly.
This revision provides the PSE&G response to IDVP OR 148.
F8.3-17 These revisions provide the PSE&G response to IDVP OR 220.
9.1.2.1, 9.1.2.2.2.2, These revisions reflect changes in the 9.1.2.3.2, 9.1.2.3.2.6, fuel pool layout due to interferences F9.1-3, 4, 41 with the cask loading pit and the reactor well gates.
This revised layout reflects as-built Hope Creek details, including the remaining space for expansion, rather than ' original details initially-specified in bid proposals.
9.1.2.5 The statement that the fuel pool liner plate is welded to scismic Category I embeds is deleted since no requirement for such a statement exists.
9.1.3.2.2.4, This revision is necessary so that the 9.1.3.5 FSAR reflects intended practice.
9.1.5.4.1.2 This revision addresses the actual preop-erational test for the polar crane.
This revision reflects industry standards and precludes duplication of field testing.
r Page 9 of 13 9.2.2.2 This addition clarifies when STACS pressure is maintained higher than SSWS pressure.
This revision provides the PSE&G response to IDVP OR'lll.
l 9.2.5.2 This revision clarifies that the Delaware River maximum temperature for which the plant can be shutdown were design assess-ment parameters only.
This revision pro-vides the PSE&G response to IDVP OR 113.
9.2.7.2, These revisions provide clarification of T9.2-7, 8 the Control Area Chilled Water Systems, i.e. the control room chilled water sub-system and the safety related panel room chilled water subsystem.
9.3.1.2 The deletion of the lead compressor auto-matic loading and unloading reference is necessary to reflect the change that all compressors are loaded at the same time.
9.3.1.4 This addition provides a clarification of the test method for oil / hydrocarbon content in the instrument air system.
T9.3-5 This change revises the Standby Liquid Control System operating pressure from 1235 to 1255 psig to reflect actual design.
T9.3-6 The addition of "(Nominal System Capacity)"
to the flow rate for the instrument gas inlet filter clarifies what the flow rate stated actually represents.
9.4.2.3 The revisions provided regarding the exhaust air transit pathway and time period are necessary to comply with the Technical Specifications.
9.4.3.1.3.b, These editorial revisions are necessary 9.4.3.2.1.3 for consistency and to properly describe the chemical laboratory system vent flow path and operation.
9.4.3.2.1.4 The steam heating coils temper the SAS supply air temperature to 60*F, not above 60*F, during cold weather.
This revision prevents the heating and cooling mode from occurring at the same time.
Page 10 of 13 S
9.4.5.1, This change revises. the drywell air cooling T9.4-14, 15 system design bases regarding air temperature, unit cooler low speed fan motor power rating and BHP, and the number of operating coolers during ILRT.
T9.4-9, 11 This change provides an update to reflect system design parameters, latest vendor data and to agree with the P& ids.
9.5.5.5 The change revises the standby diesel generator jacket water keep-warm high temperature alarm to 175 F (increasing) from 160*F (increasing).
This change is necessary to avoid spurious alarms in the standby operating mode as recommend-ed by Colt Industries.
9.5.6.2,
- This revision clarifies at what beginning 9.5.6.5 air receiver pressure starting air can be supplied to a standby diesel generator for a minimum of five consecutive engine starts and indicate at what minimum starting air system pressure a motor driven air compressor cycles on.
This change affects SER Section 9.5.6 9.5.10.1, This change deletes references to the 9.5.10.3 breathing air system's safety-related function for reactor building isolation to reficct as-built conditions.
T9.5-4 This revision changes the operating capacity to 37 gpm at 38 psig for the motor-driven diesel generator fuel oil transfer pumps to reflect actual conditions.
T9.5-11 The standby diesel generator heat exchanger lube oil is changed from SAE-30 to SAE-40.
9A (Various Sections, Various editorial revisions are provided Tables and Figures) to. correct typographical errors and various omissions from Amendment 12, including the deletion of Figures 9A-8 through 9A-14.
10.2.3.6 This change deletes the requirement to visually observe the main stop and combined intermediate valve movement once a month to reflect HCGS Technical Specification changes, Section 3/4.3.8.
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10.4.1.5.1 This change revises the condenser bypass valve backpressure setpoint which is neces-sary to match the SER and the vendor print.
i 10.4.6.2.1 This revision is provided to correctly l
indicate that conductivity cells will l
be standardized using a standard potassium i
solution.
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T11.2-10, 14, This change revises the liquid radwaste 14.2.12.1.61 process equipment pump flow rates to reflect the different modes of operation.
Regard-less, all pump capabilities are within their pump performance curves.
11.3.4, This change revises the values for calcu-l T11.3-6 lated routine doses and X/Q values l
as a result of a larger data base.
l 14.2.2.6 This revision is necessary to reflect the current composition of the Preoperational Test Review Committee, i
l 14.2.12.1.1 This revision reflects the vendor, Target l
Rock Corporation, request not to operate the SRVs, associated with the ADS, dry, i
14.2.12.1.23d This change revises the Primary Containment Atmosphere control Preoperational Test acceptance criteria to reflect current l
design configuration and to provide clari-l fication.
14.2.12.1.30 This deletion of the Diesel Generator System Preoperational Test prorcquisite regarding D/G SACS supply check valves is necessary since these valves do not exist.
14.2.12.1.47 This revision to the ECCS Integrated Initiation During a LOP Preoperational Test method is.accessary to reference Regulatory Guido 1.41.
14.2.12.1.64 This change revisos the Instrument Gas l
Preoperational Test acceptanco criteria I
to reflect system operation and testing requirements.
i 14.2.12.1.68 This change revises the Reactor Building Ventilation Prooperational Test to doloto l
the prerequisitos dealing with balancing l
and instead include those details as part of the actual test's acceptanco critoria.
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'17.2.6 This change revises the Nuclear Quality j
Assurance (NQA) Program to more accurately describe NQA involvement in station work activity and to change from a 100% review of non-safety-related work orders to a sampling based on the verified MEL data base.
l Q210.35 This question response is to revise a L
cross-reference and reference an additional I
figure to support the limiting RPV component fatigue calculations.
Q270.2.b(1)
Deletion of discussion regarding unique identification of associated circuits is necessary since they are treated and identified as class lE during their design and installation.
Q420.142
- This revised response incorporates the standby diesel generator exhaust stack roof extension which prevents thermal degradation of the roof concrete from exhaust gas impingement.
This revision impacts SER Section 9.5.8.
Q421.10
- This change provides an addition which references the revised single failure analyses performed to support air spaces less than 6 inches f or the Neutron Monit-l oring System panel and the Process Radi-ation Monitoring System Panels.
This revision provides additional inf ormation regarding SER Confirmatory Item 18.
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9421.13 This revised response reflects the latest i
optical isolator. testing results for the i
NSSS isolators to verify that they can I
withstand the maximum credible fault current /
l voltage applied in the transverse mode.
l This revision provides information necessary for closure of SER Confirmatory Item 17.
Q430.31 The response in revised to indicate the l
availability of abnormal operating pro-i l
ceduro OP-AB.ZZ-134, Loss of All Electrical Powor.
This revised response reficcts the completion l
Q430.33 I
of the UPS system testing which demonstrates the adequacy on an inverter being applied as an isolation device.
This response providos information necessary for closure of SER Confirmatory Item 30.
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Q430.ll5 This revised response changes the diesel generator air starting system air compressor i
auto start signal from 280 psi to 380 psi to reflect the vendor drawings and manual.
Q430.144
- This revised response eliminates the in-correct procedure reference and clarifies the fact that maintenance cleaning pro-cedures will be performed only if quarterly inspection results indicate a need.
This change impacts SER Section 9.5.4.1.
Q440.8 This change identifies a typographical error in referencing the correct NUREG.
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Q440.20 This revision reflects the Inservice In-i j
spection Program commitment to the ASME l
Section XI, Code, Winter 1980 Edition, which L
requires quarterly testing.
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9440.33
- The response is revised to include a Feed-water Piping Outside Containment LOCA as a Limiting Event.
This revision is related to SER Confirmatory Item 13.
Q460.4 This revision reflects information already provided to the NRC and schedulos the t
i submittal of additional information on laboratory tests.
Q480.2 This change revises the response to identify that the "Later" information in Table 6.2-16 has been provided.
Q640.10 The revised response reflects as-built plant configuration.
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0640.12 This revision is necessary to reflect l
the fact that the Emorgency Plan Proceduros l
have bacn submitted and do address tho l
torting of in-plant communications.
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Additionally, it should be noted that during the revision of Amendment l
l 12, a typographical error was discovered in the September 20, 1985 transmittal letter from R.L. Mitti (PSE&G) to W.R. Butler I
(NRC).
Pago 10 of the attachment to the lotter identified a review l
to Question 630.7 as affecting SER Section 13.2.1.4-1.A.2.1.
The correct SER Section rotorenced should have boon 13.2.1.3.
l This notico servos to identify and correct this editorial inconsistoney.
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