ML20116K894
Text
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O PSEGEEF 80 Park Plaza, Newark, NJ 07101/ 201430 8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manauer Nuclear Asaurance and Hegulation May 1, 1985 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:
l IlOPS CREEK GENERATING STATION DOCKET NO. ti0-354 FINAL SAFETY ANALYSIS REPORT, AMENDMENT 10 Public Service Electric and Gas Company (PSE&G) hereby files Amendment 10 to the llope Creek Generating Station (IICGS)
Final Safety Analysis Report (FSAR).
Pursuant to 10 CFR 50.30 (c) (1) (i) and 10 CFR 51.40 (b) this filing consists of sixty (60) copies of PSAR Amendment 10.
In accordance with 10 CFP. 2.101 (a)(4) and 10 CFR 50.30 (c)(1), three (3) signed originals of the required affidavit are enclosed.
Amendment 10 to the llCGS FSAR contains: (1) text changes due to resolution of Safety Evaluation Report open items, (2) updated drawings tabulated in FSAR Section 1.7 and (3) general revisions to the PSAR text.
A brief summary and explanation for each change is provided in the attachment to this letter.
Should you have any questions on the subject filing, do not hesitate to contact us.
Very truly yours, 50hk $
34 M
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-[0 3 Enclosures C
Mr.
D.
- 11. Wagner 4
8 USNRC Licensing project Manager M P84 132/07 1 p
The Ener0y Peoplo m
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ATTACHMENT I
AMENDMENT' 10 TO HCGS FSAR DESCRIPTION OF REVISIONS BY FSAR SECTION
.T.l.3-1 Design power level for Hope Creek is revir.ed based on plant specific ECCS analysis.
HCGS SER page 1-3 is affected.
T.l.3-4 The calculated maximum suppression chamber
, pressure following LOCA blowdown is corrected to be consistent with HCGS SER page 6-6.
T.l.3-8 Revised.to reflect deletion of the RHR steam condensing mode.
l T.1.7-1.
These tables are revised to reflect recently l
T.l.7-2 added drawings / figures and to reflect recent L
T.1.7-3 revisions of drawings / figures listed.
1.8 (R.G.1.29 ) The description of inspection of field work is clarified to address the period prior to initiation of the R.G.1.29, Rev. 3, program at HCGS.
1.8 (R.G.1.75) Justification is added for the use of conduit, metal-clad cable, armor-clad cable, radio-antenna cable, and free-air cable.
Test results are also added as a basis for establishing minimum separation criteria for these' items.
This change affects HCGS SER Outstanding Issue.No. 7 and Confimatory Issue No. 29.
1.0 (R.G.1.108) This change reflects the change in schedule for the 24-hour full load diesel generator preoperational test.
This change was made to accommodate the R. G. 1.108 requirements to test the sequencing' circuitry under hot' conditions (see.also 8.3.1.1.3.10).
1.10.2
-(I.A.3.1),The response is revised to' indicate that.requalification program requirements have been outlined in-the' Nuclear Department' Training procedures. _This-information
.affects HCG 8 SER Outstanding Issue No.-12d.
1.10.2 (I.C.1) The response-is' revised to reflect inclusion of. the Procedure Generator Package in the F8AR, which affects HCG 8 SER' Outstand-ing Issue No.HL4.
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1;1052 (I.D.1) The response is. revised to reflect completion of the detailed control' room review for human factors considerations.
'1.10.2 (II.B.4) The response is revised to indicate that a program has been implemented for training of all plant operating' staff in mitigating core damage.
This information af fects HCGS SER Outstanding Issue No.12d.
-(See also the revised response to question 630.4).
g 1.10.2 (II.K.3.27) The response is revised to indicate the common reference point for instruments measuring reactor vessel water level.
1.10.2 (II.K.3.30) The response is revised to reflect NRC acceptance of the General Elec-tric small break model.
- T.1.11-1 Additional differences from SRP 9.5.1 (Rev.
l
- 3) and BTP CMEB 9.5-1, C.1.c(2), are listed l
for consistency with the revision to HCGS FSAR Section 9.5.1.6.1.
( See 9.1. 5. 6.1 ).
T.1.11-1
'SRP differences for the fire detection system and fire sump are clarified.
1.14.1.27.2 The response is revised to reflect completion j
of the HCGS specific ECCS analysis, which is HCGS SER Confirmatory Issue No.14.
L 1.14.1.47.2 The. response is revised to identify the HCGS L
Emergency Operating Procedure which contains the necessary steps for mitigating an ATWS l
. event.
l 1.14.1.71.2 The response regarding criterion 5.a is revised to reflect that the' bypass vent valves used = for purging have been changed to air-operated valves that close in less than 15-seconds, and.that the existing dose anal-o l
ysis for purging events is conservative and l
requires no revision.
It should be noted that there is a-discrepancy in the HCG 8 SER l
regarding these valves.
SER page 6 '
[
erroneously. indicates 'that these are ' motor-operated valves, while SER page 6-24 cor-rectly states that they are air-operated.
(See also 6.2,.5.2.2).
1.14.1.108.2
'The response is revised to reflect completion of the HCOS-specific ECCS' analysis, which is HCG 8 -SER Confirmatory Issue No.14.
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1.14.1.111.2 The response is revised to clarify control rod friction testing requirements and to change the exposure limit for friction test-ing from 30,000 mwd /t to 36,000 mwd /t.
2.3.5.3.6 Information is added regarding horizontal dispersion coefficients for clarification of the response to question 451.17.
T.3.2-1 The table is revised to identify the appli-cable design code for the torus water cleanup pumps, and to correct the description of the fuel pool cleanup holding pumps for consistency with Technical Specifications and the applicable P&ID.
T.3.2-1 The entry regarding quarrystone revetments is deleted.
T.3.4-2 The table is revised to correct the type of flood protection provided for the west por-tion of the south wall of the reactor building.
3.6.1.2.1, The section is revised and associated figures Fig. 3.6-34 are deleted because the CRDH system is to be analyzed as a moderate energy system in accordance with SRP 3.6.2.III.2.c acceptance criteria.
Fig. 3.6-9, These figures are revised for consistency Pig. 3.6-41 with main steamline break analysis calculations.
l 3.9.5.1.1, Text and associated tables are revised to T. 3.9-5 b,-5 c reflect the results of single-plant (i.e.,
HCGS Unit 2 cancellation) seismic loads on the RPV internals analysis.
l 3.11.1, Text and table are revised to include addi-3.11.2.7, tional information on equipment qualification l
T.3.11-8 in response to NRC RAI, dated November 3, 1984, and in partial response to HCGS SER Outstanding Issue No. 2.
l T.3.11-4 A new table is added identifying mechanical l
equipment selected for harsh environment qualification.
This is also in response to l
SER Outstanding Issue No. 2.
i 5.2.3.2.3 lThe description of material compatibility with reactor coolant is revised to include examples of systems in contact with reactor coolant.
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5.2.5.4.1 Rovised pump capacities are provided for the equipment sump and floor drain sump pumps.
T.5.2-2 The table is revised to show which code casos are subject to additional requirements in Regulatory Guidos 1.84, 1.85, and 1.147.
Also, code caso N282 is added to the table.
This information is pertinent to HCGS SER Confirmatory Issue No. 7.
6.2.1.1.2, The description of the operation of contain-6.2.1.1.4 mont vacuum relief valves is clarified for consistency with the negative pressure design ovaluation.
6.2.1.1.3 The maximum calculated accident value for l
supprossion chambor pressure is changed to 27.5 psig from 28.1 psig based on HCGS-specific analysis.
6.2.1.1.4 The description of the sizing basis for the containment vacuum relief valves is revised to reflect the correct design negative pres-I sure.
This information affects the descrip-tion in HCGS SER Section 6.2.1.4.
6.2.3.2.3, The containment bypass leakago analysis is Fig. 6.2-51 revised to stato that a water seal will be maintained in the feedwater system in the short-term following a LOCA to provent bypass leakage.
This information applies to HCGS SER Confirmatory Issuo No.13, and was provided to the NRC staff in a letter from R.
L. Mitti to A. Schwencer, dated April 22, 1985.
6.2.4.3.2 The description of the traversing incore probe guide tubo linos is revised to 7eflect the change in isolation valves from motor-operated to solenoid-operated.
This nforma-(
tion affects HCGS SER Section 6.2.4.
6.2.5.2.2 The soction on purging and related figuros Fig. 6.2-28 are revised to reflect the change in the 2-inch globe valvo from motor-operated to air-operated.
This information af fects HCGS SER Section 6.2.4.1 as described under 1.14.1.71.2 of this attachment.
6.2.5.2.5, The HOAS samplo locations are revised as Fig. 6.2-50 shown.
T.6.2-6 The units for secondary peak supprossion chamber prosauro are corrected to road " psia" instead of "psig."
This information affects HCGS SER Section 6.2.1.3.2.
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.T. 6. 2-16,
L The table is revised to correct the applic-able general design criterion for' probe guide i
tube penetrations.
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_6.3.2.2.6, Reference.to the RHR steam condensing mode is L
6.3.2.6 deleted.
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6L3.3.3 The discussion of single failure considera-l tions is revised to. reflect the results of l
HCGS-specific ECC8 analysis.
1 6.3.3.7.3 sections describing line break calculations are. revised to reflect the results of the HCGS-specific ECCS analysis.
6.3.8
-The correct report number is provided for L
Reference 6.3-1.
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Tables 6.3-l' The tables and figures are revised to reflect l
thru 6.3-4; the results of the HCGS-specific ECC8 l
Figs. 6.3-4, analysis.
l 6.3-5, 6.3-9, 6.3-11, 6.3-14 thru 6.3-62 T.6.4-6 The east / west coordinate for the M8 Tunnel Blowout Panel is corrected.
6.7.2.1, The descriptions of operation and testing of 6.7.2.3, the MSIV sealing system are clarified.
l 6.7.3.5,
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6.7.5 7.3.1.1.1, References to the RHR steam condensing mode 7.4.1.1.1, are. deleted.
7.4.1.1.2 l
7.4.1.1.2 The description of SLC operation is corrected to indicate that both loops automatically l
initiate, provided that APRM power is not
(
downscale.
-i 8.1.4.14.3.1 This section is revised to provide justifica-l
. tion for 18-inch vertical separation between i
trays and to demonstrate that the tray cover is an of f active barrier for separation 'pur-l poses.
This change affects HCGS SER Out-l standing Issue No. 7.and Confirmatory Issue No. 29 M P85.96/01 5-srd t
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18.3.1.1.3.10 The preoperational Emergency Diesel Generator
'(EDG) ' test -description is revised to include l
a 24-hour full load test, followed by a gen-l' erator load shedding test, including a test of EDG capacity to withstand the loss of the largest single load.-
References to 4-hours of no load EDG opera-tion prior to performing the full load test are deleted.
Reference to the test descrip-tion in Section 14.2.12.1.47 is added.
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8.3.2.1.2.1, Battery rating revised from 560 to 577 ampere 8.3.2.1.2.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for consistency between referenced t
sections and FSAR Figure 8.3-8.
T.8.3-1, Revised to incorporate modified operating 2,3,4,5,66 loads.
T.9.1.5.3.2, Revised to provide the addition of the new T.9.1-12,14, fuel containers which weigh approximately one 22,623 (1) ton and are therefore, considered heavy Fig. 9.1-32 loads.
This change affects SER Supplement 1, Section 9.1 and SER Appendix G.
4 9.2.8.2 Revised _RACS description to state that the emergency instrument air compressor heat exchangers are not automatically provided
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with RAC8 cooling water during an LOP.
9.3.1.4 Revised to indicate that the filters will be replaced quarterly rather than inspected quarterly.
9'.3.2.2.2.11, Revised date for procedure availability.
9.3.2.3.2 9.3.6.4 PCIGS outlet filter to be replaced quarterly rather than inspected quarterly.
9.4.7.5 Revised to indicate that 8WIs ventilation l
system includes two-(2) position dampers not L
modulating dampers.
- 9. 4.8. 2.9 a Revisions to Circulatory Water Pumphouse l
description.to be consistent with logic dia-gram-and system' design.
9.5.1.1.6 Revised to clarify that there are two cable spreading rooms.
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r 9.5.1.1.14 Revised to add automatic preaction sprinkler system to cover high concentration of cable trays outside cable spreading room, and to clarify that not all areas that contain cable concentrations have a ventilation system to remove smoke.
9.5.1.2.6 Revised to a description for the manual deluge systein ir. the control equipment room
. mezzanine.
9.5.1.2.7 Revised description of operation for manual preaction water spray systems.
9.5.1.2.8 Revised to indicate what type of devices are used to actuate preaction sprinkler systems and to provide a description of the preaction sprinkler system in the cable spreading room.
9. 5.1. 2. 9 Revisions provided to indicate the availabil-ity of additional lengths of fire hose to be used by the Fire Brigade to reach non-safety related areas.
9.5.1.2.13 Revised to add Halon 1211 extinguishers to l
cover the control room, computer room, and l
remote shutdown panel room for class A, D, and C fires.
Also, revised to indicate addi-l tional sizes of multipurpose dry chemical extinguishers that are being provided for the administration facility and guardhouse.
l 9.5.1.2.15 Revised to clarify description of fire and smoke detection system indicating that this l
i system is not part of any detection system l
used to actuate fire suppression systems.
Also, deleted description of thermal detector operation since this system does not use thermal' detectors.
Also, added continuous line-type heat detectors which were added in the torus area to meet Appendix R require-ments.
Also, indicated that areas where photoelectric beam type detectors are located i
i in the Reactor Building are safety-related areas and clarified that, in general, areas l
with combustible loading greater than 8000 l
Btu /ft2 are provided with fire and smoke i
detection systems.
9.5.1.2.19 Revised to indicate that the type of portable i
fire extinguishers to be used in' the main control room is Halon 1211.
9.5.1.2.20 Revised to indicate that there are two (2) cable spreading rooms.
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9.5.1.4.1.4 Revised description of actual tests performed on CO2 system.
9.5.1.4.2 Revisions to operational testing and inspec-tion for the fire protection system.
9.5.1.6.1 Revisions are provided to list additional exceptions and dif ferences to BTP CMEB 9.5-1, Rev. 2, C.1.c(2), regarding failures impair-ing fire suppression capability.
9.5.1.6.10 Revised to indicate continuous line-type heat detection is provided for the safe shutdown cable trays in the torus area.
Also, revised to delete sentence which states cable trays are normally accessible for manual fire fighting.
Also, added references to the addition of automatic water suppression sys-tems which are being proposed for certain safety-related areas that havo high concen-trations of cable.
9.5.1.6.14 Revised to indicate differences and clarifi-cations to BTP regarding fire detection sys-tems complying with the requirements of Class A systems.
(Sco Table 1.11-1, Page 22 of 27, also).
9.5.1.6.17 Revised to provido justification for not locating tank inside the fire pump house or heat tracing tank.
Also, revised to indicate that fire pump system meets NFPA 20 requirements.
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9.5.1.6.20B Revised to add clarification and differences to the BTP regarding valves in the fire water systems.
(Sco Tablo 1.11-1 also).
9.5.1.6.21 Revised to add difference to BTP regarding IICGS fire hose stations that have an addi-tional unconnected 50-foot of hose to reach cortain areas of the plant.
(See Tablo 1.11-1 also).
9.5.1.6.25 Revised to add reference to addition of now manual delugo system in control equipment room mozzanino.
9.5.4.2 novisod description of diosol fuel oil fill lino filter to reflect as-built conditions.
(Soo 0430.87 also).
9.5.4.2 Revised SDG description to indicato the cor-rect ongino rated load and manufacturor's description.
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- 9.5.7.2 LRevised' to indicate that there will be a
' fourteen day 7 supply of lube oil reserve on site for the SDGs.
This responds to HCGS SER Outstanding Issue No. 10.
-(See 0430.131 also).
9.5.10,
' Revised to clarifyfand correct Breathing Air 9.5.10.2 System description.
9.5.10.3 1 Revised to indicate the as-built condition of the breathing air system breathing air line
^ that penetrates the reactor building.
Table 9.5-2 Revised to remove equipment unloading bay as being covered.by an automatic' wet pipe sprinkler system'aince it is listed in the table elsewhere 'as being covered by an auto-matic preaction sprinkler system.. Also, revised to add new sprinker systems. to cover high cable tray concentrations, new manual deluge system for the-control. equipment room
' mezzanine, and to reflect the placement of portable extinguishers.
Table 9.5-3 Revised to include air bottles and LPG bottles located on site.
Table 9.5 Revised to correct maximum or actual hose stream flows.
9 A. 6.14, Revised to clarify the SWIS Division I fire 9A.6.17 area.
10.2.3 Revised testing and inspection of turbine control valves per plant' specific 1 technical specifications.
(See 0430.167 also).
e 11.4.2.3 Revised temperature (i.e., increase)-used to prevent dissolved solids from crystallizing in tho' bottom tank prior toisolidification.
11.4.2.4.1 Revised temperature (i.e.,
increase) for mixing of solid radwaste with asphalt.
Table 11.4-2 Revised design temperature (i.e., decrease) for solid waste' system centrifuge feed tank.
Table 11.4-3.
Revised component data,for solid waste system.
Table.ll.4-4 Revised component data for solid waste.
system.
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Lil.5.2.2.5' Revised description of liquid radwaste dis-
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charge to clarify that dilution of flow is by cooling tower. discharge only.
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Chapter:13 Revised to add listing of new Appendix 13L T.O.C.-
'whichiincorporates a Procedures Generation Package (PGP).' This.information affects HCGS SER Outstanding Issue.No. 14.
Table.13.1-la Revised to add resumes-for Vice President -
NuclearEand Manager of Public Information -
- Nuclear and to update resumeoof the Manager -
Nuclear Training.
This Jaformation affects HCGS SER Outstanding Issue No. 11.
13. 2. l ~. l. 4.1 Revised.to clarify training requirements for
' Chemistry personnel.
13.2.1.1.4.2 Revised tol clarify: training requirements for'
' Instrumentation and Control personnel, and editorial revisions.
13.5.2.1.3 Revised to add reference - to new Appendix 13L which provides the PGP, and editorial revisions.
Appendix 13L-New appendix added to FSAR; Procedures Gen-erhtion Package (PGP).
This information is applicable to HCGS_SER. Outstanding issue No. 14.
14.2.1.1 Revised description'of Phase I' Construction Verification Test Program-to clarify system turnover prerequisites, and' provide correct corporate titlos.
14.2.2.2.1.1 Revised-to add startup director's position to organizational description.
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14.2.2.2.6 Revised.to replace discussion of Bechtel j-Pield Startup Superintendent with: discussion of' Principal Startup Engineer - Construction
. Completion.
.14.2.2.4.1 Revised-title of PSE&G Project ~ Construction Manager to.PSE&G Construction Engineer - Site Construction. ' Also, revised list of ' issues.
- requiring interface with Startup1 Manager.
k 14.2.4.2:
- Revised to delete Project Construction j.
. Manager - Hope Creek from approval cycle for l
system. turnover-documentation acceptability.
14.2.5.1 Revised to provide description of approvals required.for' Phase I and-II, test 2results.'
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K 14. 2.12.1.17 '
Revised.to change air flow balancing from a
.. test-prerequisite to'a test acceptance cri-terion'for the~ Auxiliary Building-(Radwaste Area) HVAC preoperational test.
Also,-
revised to add preliminary air balance as a prerequisite.
Also, deletes operability of
-the charcoal filter _ fire protection system as l
.a prerequisite.
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1.4.2.12.1.19 1 Revised to change test = prerequisite for air flow -balancing into a test acceptance cri-terion for. the = Control Wiring Area HVAC pre-operational test.
Also,. revised to add preliminary air balance as a prerequisite.
Also, revised to clarify test method descrip-
. tion and acceptance criteria description for HVAC.preoperational testing.
14.2.12.1.20 Revised to change that prerequisite for air
' flow balancing into.a test acceptance cri-terion for the Service Area HVAC preopera-tional. test.
Also, revised to add preliminary air balance as a prerequisite.
14.2.12.1.21 Revised to add preliminary air balance as a test prerequisite and to add final air balance as a test acceptance criterion for
-the D/G Area HVAC preoperational test.
14.2.12.1.24 Revised'to change test prerequisite for air flow balancing into a test acceptance cri-terion for the Drywell _ Ventilation 'preopera-tional test.'
Also, revised to add preliminary air balance as a prerequisite.
14.2.12.1.25 Revised to change test prerequisite.for air flow balancing into a, test acceptance'cri-terion for'the Filtration,-Recirculation, and
- Ventilation System preoperational. test.
Also,-revised to add' preliminary air'balanc-ing as a prerequisite and to' delete operabil-e o
ity of the charcoal filter fire protection system as a prerequisite.
14.2.12.1.30:
Revised to indicate' objectives, prerequi-sites,. test method, and acceptance criteria for Emergency Diesel ~ Generator's preopera-
'tional testing.
14.2.12.1.31 Revised to correct test - prerequisite for MSIV Sealing System'preoperationalitest to include a _ Type C'-leak _ rate test' on MSIVs rather ' than Type =B test.
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/14.'2.12.1.38-Revised to delete emergency. beacon light
- operability verification from the In-Plant 1 Communication preoperational-test objectives.
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14.2.12.1.47:
Revised to\\ indicate objectives and test method for ECCSJIntegrated Initiation During LOP.preoperational' testing.
14.2.12.2 Revised to
- delete discussion of Level 3 of acceptance.. criteria for Startup Tests.
t._
114 ~. 2.12. 3 Various-startup ~ procedures revised per revised-specifications, restrictions, etc.
14.2.12.3.33 Revised to delete' references to the steam
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~ condensing modeifor'the-RHR system.
- Also, p
Jrevised to add new test' objective to demon-
' strate RHR' capability to reduce suppression-i pool - temperature Ebelow limits following
. blowdown.
[
. Fig. 14.2-2 Revised titles in the Startup Group Interf ace diagram.
4 I-15.2.9.3
-Revised to correct pump division failure to
.be consistent with HCGS.having four.(4) divisions.rather than two (2).
Table 15.6-7 Revised to reflect results of the HCGS-specific ECCSl analysis.
15.8.1-
. Revised to indicate-availability of EOP for i
Reactor Controv during an ATWS event.
a i'
17.2.2 Revised'to ad URe.*ulatory. Guide 1.26 to OA i
program as applica.le.
- 0210.1
- Revised to indicate the-deletion 3of Figure 3.6-34.and ; provide information fregarding the F
CRDH system analyzed as,a mcderate energy system as. described in FSAR Gection-
-3.6.1.2.1.15 in accordance wit'. the accep--
tance criteria' listed'in SRP J,G.2.III.2.c.-
(See 3.6.1.2.1.15-and Fig.--3.6-34 also).
0210.2 Revised'to reforecast'.' commitment from December 198 4, : to - June l1985.
r 0210.15' See'0210.1:above.
O210.20-Revised toL.reforecast commitment from January.
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~1985 to:May!1985.
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0210.21' Revised"to reforecast1 commitment from
' December 198 4: to - April.:1985. -
i M:P85 9.6/01'.12-srdl
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0421.3 Revised. to reflect deletion of RHR steam con-densing mode of operation.
0421.18 Revised to include NRC acceptance of the BWR Owner's Group setpoint methodology program.
This is in response to SER Confirmatory Issue No. 16.
0430.33 Revised to clarify description of relief valves.
This is in response to SER Confirma-tory Issue No. 27.
Also, revised to add loads and reflect submittal of test report.
0430.'40 Revised to indicate.the use of written proce-dures to perform periodic testing of Class lE safety systems.
0430.87 Revised description of diesel fuel oil fill line filter to reflect as-built conditions.
(See 9.5.4.2 also).
0430.94' Revised to reforecast commitment from January 0430.111 1985 to April 1985.
0430.133-0430.131 Revised for consistency with PSE&G commit-ments regarding delivery and storage of diesel generator lube oil.
This information af fects HCGS SER Outstanding Issue No.10.
(See also 9.5.7.2).
0430.167 Revised to reflect change in testing and inspection of turbine control valves per plant-specific technical specifications.
(See alco 10.2.3 ).-
0440.0, Revised to reflect completion of the HCGS-0440.27 specific ECCS analyses, which is.HCGS SER Confirmatory Issue No. -14.
T.440.33-1 The' footnote.to the' table is revised to clarify the intended meaning of " relief valves" as used in this table.. This informa-tion'affects'HCGS SER" Confirmatory' Issue 2No.-27.
0480.4 The response is revised to reflect submittal ofEthe HCGS Plant-Unique Analysis' Report (PUAR) to NRC in a letter from R.
L. Mittl-to A.-Schwencer, dated January 8, ' 1985.
This information affects'HCGS SER Confirmatory Issue No.:2.-
M'.P85 96/01 13-srd' l
0480.14-Rev'ised.to reflect the add'ition of a crosstie to1the feedwater line fill network to main-
- tain.a water seal:.in~the event of a LOCA.
- This information affects HCGS SER Confirma-tory. Issue No.-13.
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0480.31 Revised for consistency with revised Figure:6.2-28 showing _ test valves to be used
- for 10; CFR 50, Appendix J, Type C testing.
0630.4-
- Revised to ' reflect inclusion of the Proced-ures Generation Package in the FSAR and to indicate the' status of core damage mitigation
- training programs for technicians and man-agers. -(See also 1.10.2.II.B.4).
-0640.10
-Revised to indicate that'the 24-hour' diesel generator full load-preoperational test is to be conducted-in-conjunction ~with the ECCS integrated initiation'during loss-of-offsite-power test..
(See also 8.3.1.1.3.10 and 1.8 (R. G.11.108).
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Revised to show that SRV. position indication is not Q-listed,Jand to provide a correct reference.
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.s UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-354 PUBLIC SERVICE ELECTRIC AND GAS COMPANY AMENDMENT 10--
FINAL SAFETY ANALYSIS REPORT Public Service' Electric and Gas Company hereby submits AMENDMENT 10 to the Hope Creek Generating Station Final Safety Analysis Report (FSAR).
The HCGS FSAR amendment con-sists of text changes due to. resolution of Safety Evaluation Report open items, updated drawings tabulated in FSAR Section 1.7, and general revisions to the FSAR text.
The matters set forth in this amendment are true to the best of my knowledge, information, and belief.
Respectfully submitted, Public Service Electric and Gas Company By:
R.7. Eckert Senior Vice President -
Nuclear-and Engineering Sworn to and subscribed before me,_a Notary Public
/5 day of New Jersey,.this 5
of May.1985 Wi J/h
~
\\ t.
' ' I.,<
l DAVID K. BURD 7_
NOTARYPUBUC OFNEW JERSEY Expires 10-23-85 t
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