ML20113D466

Forwards Current List Providing Status of Tech Spec Issues Identified in Section 16 of Ser.Items for Which No Confirmation of Status Received Identified as Complete & Considered Closed Unless Otherwise Notified

ML20113D466
Person / Time
Site:	Hope Creek
Issue date:	04/10/1985
From:	Mittl R Public Service Enterprise Group
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8504150311
Download: ML20113D466 (58)

Text

{{#Wiki_filter:- - - O PS G Cbmma Pubhc Serwce Electnc and Gas 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 Regulation April 10, 1985 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention: Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen: SAFETY EVALUATION REPORT TECHNICAL SPECIFICATION ISSUES HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Attac hment 1 is a current list which provides a status of the Technical Specification Issues identified in Section 16 of the Safety Evaluation Report (SER). Items identified as " complete" are those for which PSE&G has provided responses and no confirmation of status has been received from the staff. We will consider these items closed unless notified othe rwis e. In order to permit timely resolution of items identified as " complete" which may not be resolved to the staff's satisfaction, please provide a specific descripticn of the issue which remains to be resolved. Enclosed for your review and approval (see Attachment 3) are the resolutions to the SER Technical Specification Issues listed in Attachment 2. Also enclosed ( Attachment 4) for your use and incorporation into the Hope Creek Generating Station Draft Technical Specifications are five (5) sets of the following revised Hope Creek Generating Station Draft Technical Specification pages: 8504150311 850410 PDR ADOCK 05000354 E PDR f700 MP8 5 81 02 1-vw l ll t f The Energy Peopka 95 4112 (3W 4 84

'k Director.of Nuclear Reactor Regulation 2 4/10/85 Page: 3/4 6-49 3/4 6-50 3/4 6-51 3/4' 7-5 Insert A to pg. 3/4 7-5 These pages are submitted as Revision 3 to the Hope. Creek Generating Station Draft Technical Specification and have been revised in accordance with the resolutions to the SER Technical Specification Issues provided in Attachment 3. Also_ included are copies of the updated Hope Creek - Generating Station Draf t Technical Specification List of Effective Pages (LEP). Should you have any questions or require any additional information on.these items, please contact us. Very truly yours, Attachments C D. H. Wagner USNRC Licensing Project Manager (w/ attach. ) A. R. Blough USNRC Senior Resident Inspector-(w/ attach.) MP85 81 02 2-vw w ,.c- - - - - SER TECHNICAL SER R. L. MITIL TO : SPECIFICATION SECTION A. SCHWENCER ISSUE NUMBER SUBJECT STATUS IRITER DATED 1 2.4.11.2 Service water intake tenperature Cmplete 4/10/85 2 2.4.14 Closing of doors and hatches Couplete 4/10/85 3 3.9.6 Pressure isolation valves Open 4 4.4.4 - Thermal-hydraulic instability Cmplete 4/10/85 5 4.4.4 Single-loop operation Cmplete 4/10/85 6 4.4.5 Crud effects Caplete 4/10/85 7 4.4.6 Icose parts monitoring system Cmplete 4/10/85 channel operability 8 5.2.2 Safety / relief valve (SRV) test Open progra 9 5.2-Reactor coolant pressure boundary Couplete 4/10/85 l leakage rates 10 5.4.6 Reactor core isolation cooling pung Complete 4/10/85 testing t 11 5.4.7 Residual heat removal system pump Conplete 4/10/85 operability 12 6.2.1.6 Torus /drywell vacuum breaker and Open l vent system testing l 13 6.2.1.6 Vacutn breaker position indication Open j accuracy 14 6.2.3 Testing of inleakage rate and draw-Couplete 4/10/85 down time l 15 6.2.4.1 Isakage testing for valves with Open l resilient seals l 16 6.2.6 Containment isolation valve leakage Open MP85 81 02 4-vw Page 1 of 4. (Cont'd) SER TECHNICAL SER: R. L. MITIL TO SPECIFICATION SECTION A. SCHWENCER ISSUE NLNBER SUBJECT STATUS IEITER DATED 17 6.2.6, 6.7, Main steam isolation valve leak rate Open 15.6.5.2 testing 18 6.2.6 Various valve leak rates Open 19 6.3.4.2 Emergency core cooling system Open (ECCS) subsysten flow rates 20 6.3.4.2 ECCS subsystem operating sequence Open 21 6.5.1.3 Water seal bucket drain tap Ccmplete 4/10/85 surveillance Open 22 7.2.2.3 Testability of plant protection system at power Open 23 7.2.2.8, Anticipated transients without 7.6.2.2 scram mitigation Open 24 7.2.2.9 Reactor mode switch Open 25 7.3.2.3 Freeze protection of water-filled lines 26 7.4.2.3 Remote shutdown system operability Open 27 7.6.2.1 Iw-pressure /high-pressure systems Open interlocks Open 28 7.6.2.3 Average power range monitor electrical protection assenblies open 29 7.7.2.3 Nonsafety-related equipnent Open operability 30 8.3.1.3 Diesel generator connected loads Canplete 4/10/85 31 8.3.1.7 Inad sequencer logic Cornplete 4/10/85 32 8.3.2.7 DC system monitoring Complete 4/10/85 MP85 81 02 5-vw Page 2 of 4

) Attachnent 1 (Cont'd) SER TECHNICAL SER R. L. MITTL TO SPECIFICATION SECTION A. SCHWENCER ISSUE NUMBER SUBJECT STATUS IEITER DATED 33 8.3.3.3.5 Testing of breaker time-overcurrent Open trip characteristics 34 8.3.3.4.1 Periodic syste testing Complete 4/10/85 35 8.3.3.4.2 Ioad sequencer testing Cmplete 4/10/85 36 8.3.3.5.4 Testing of fuses Complete 4/10/85 37 9.1.3 Fuel pool cooling system ptmps Open 38 9.2.1 Station service water ptmp testing Complete /10/85 4 39 9.2.2 Safety auxiliaries cooling system Coroplete 4/10/85 and reactor auxiliaries cooling system ptmp availability 40 9.2.2 Safety auxiliaries operability to Open ensure diesel generator cooling 41 9.2.7 Control area chilled water system Open availability 42 9.3.1, Air quality testing Open 9.3.6 43 9.3.2 Core damage estimate procedure Open 44 9.5.1.5 Fire watch Ccmplete 4/10/85 45 10.2 Turbine steam valve inspection Ccmplete 4/10/85 46 10.4.4 Turbine bypass valve surveillance Conglete 4/10/85 47 15.2 Turbine bypass syste and level Open 8 high-water trip performance 48 15.4.9 Scram speed Open j 49 15.6.4 Primary coolant activity Open i 4 E MP85 8102 6-vw Page 3 of 4 i

Attachnent 1 (Cont'd) SER TECHNICAL SER R. L. MITTL 'IO SPECIFICATION SECTION A. SCHWENCER ISSUE NUMBER SUBJECT STATUS IEITER IRTED 50 15.6.4 Main stean isolation valve closure Conglete 4/10/85 time 51 15.9.3 SRV failure reporting Couplete 4/10/85 52 15.9.3 Automatic depressurization system Open logic l l 'l DJD:vw MP83 81 02 7-vw Page 4 of 4

4 ATTACHMENT 2 Technical Specification Issue SER Section Subject 1 2.4.11.2 Service water intake taperature 2 2.4.14 Closing of doors and hatches 4 4.4.4-Thenral-hydraulic instability 5 4.4.4 Single-loop operation 6 4.4.5 Crud effects 7 4.4.6 Icose parts monitoring system channel operability 9 5.2.5 Reactor coolant pressure boundary leakage rates 10 5.4.6 Reactor core isolation cooling punp testing 11 5.4.7 Residual heat rsoval system punp operability 14 6.2.3 Testing of in-leakage rate and drawdown time 21 6.5.1.3 Water seal bucket drain tap surveillance 30 8.3.1.3 Diesel generator connected loads 31 8.3.1.7 Inad sequencer logic 32 8.3.2.7 DC system nonitoring 34 8.3.3.4.1 Periodic system testing 35 8.3.3.4.2 Icad sequencer testing 36 8.3.3.5.4 Testing of fuses 38 9.2.1 Station service water punp testing 39 9.2.2 Safety auxiliaries cooling system and reactor auxiliaries cooling system punp availability 44 9.5.1.5' Fire watch 45 10.2 Turbine steam valve inspection 46 10.4.4 Turbine bypass valve surveillance 50 15.6.4 MSIV closure time 51 15.9.3 SRV failure reporting

ATTACHMENT 3

SER Technical Specification Issue-No. 1 (SER Section 2.4.11.2) Service Water Intake Temperature The Hope Creek Environmental Report indicated a maximum Delaware River water temperature of 88.5'F in August 1983. The applicant has stated that.the maximum intake tempera-tures, as discussed in RG 1.27, that will allow the plant to safely shutdown under normal and emergency' conditions are 91.6'F and 90.5'F, respectively. The staff concludes that the plant meets GDC 44 with respect to the thermal aspects of the UHS, -but will require a Technical Specification to monitor intake water temperature at 6-hour intervals when . the intake water temperature exceeds 85'F.

Response

HCGS Draft Technical Specification Section 3.7.1.3, Ultimate Heat Sink, has been revised to provide the above surveil-lance requirement. I MP 85 64/07 1-mr

PLANT SYSTEMS. ULTIMATE HEAT SINK (0;;ti.. ;') LIMITING CONDITION FOR OPERATION

3. 7.1. 3 The(ultimateheatsink)shallbeOPERABLEwith:

river A minimum (5::f ) water level at or above elevation f7(,') M [ a. h,M8W4HiGG datum, and 90.5 An average (19N$) water temperature of less than or equal to g )'F. l / b. (c. (At !:::t) (Tre) OPER^"LE :::!%; terer '- :.) l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and *. l ACTION: With the requirements of the above specification not satisfied: a. In OPERATIONAL CONDITIONS 1, 2 or 3, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours. l .5ACS b. In OPERATIONAL CONDITIONS 4 or 5, declare the-inNA&W. system and the plant service water system inoperable and take the ACTION required s by Specification 3.7.1.1 and 3.7.1.2. c. In Operational Condition ", declare the plant service water system inoperable and take the ACTION required by Specification 3.7.1.2. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS

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v SER Technical Specification Issue No. 2 (SER Section 2.4.14) Closing of Doors and Hatches on the basis of its review in accordance with SRP Section 2.4.14, the staff concludes that a Technical Specification or Emergency Operating Plan will be required to ensure that all watertight doors and hatches to the safety-related facilities are closed and secured well in advance of a hydrologic event that is predicted to produce water levels (including wave runup) in excess of el 10.5 ft. MSL at the service water intake structure or el 13.0 ft. MSL at the power block. As discussed in.Section 2.4.11.2, the staff will also require a Technical Specification to monitor the service water intake temperature.

Response

HCGS Draft Technical Specification Section 3/4.7.3, Flood Protection, incorporates the above requirement to secure all watertight doors and hatches. The requirement to monitor service water intake temperature is addressed in revised Technical Specification Section 3.7.1.3 provided in the response to SER Technical Specification Issue No. 1. MP 85 64/07 2-mr

SER Technical Specification Issue No. 4 (SER Section 4.4.4) Thermal-Hydraulic Instability As a result of its review of the thermal-hydraulic stability of the Hope Creek core, the staff requested the applicant to submit a plant-specific evaluation addressing his position with respect to the GE recommendations in SIL-380 for providing protection against the potential for thermal-hydraulic instability, including a Technical Specification that will restrict operation in regions of potential in-stability (e.g., natural circulation and single-loop operat-ing conditions) and/or provide for surveillance and correc-tive action under conditions of marginal stability. By letter dated September 21, 1984, the applicant committed to implement Technical Specifications consistent with the GE recommended Technical Specifications to address the concern .of thermal-hydraulic stability. The applicant also in-dicated that Hope Creek will operate in two-recirculation loop operation. On the basis of the applicant's statement that he will implement a Technical Specification that will restrict operation in regions of potential instability and provide surveillance and corrective actions under conditions of marginal stability, the staff concludes that the appli-cant will have a Technical Specifications to satisfactorily resolve the concerns of thermal-hydraulic stability and, therefore, the core thermal-hydraulic stability design is acceptable.

Response

HCGS Draft Technical Specification Section 3/4.4.1, Recircu-lation System, restricts operation in regions of potential instability and provides surveillance and corrective actions under conditions of marginal instability. I l Mp 85 64/07 3-mr l I l l k

'SER Technical Specification Issue No. 5 (SER Section 4.4.4) I Single-Loop Operation Since no analysis has been presented for MCPR limits or stability characteristics for single-loop operation, the staff will require a Technical Specifications that prohibits single-loop operation unless supporting analyses are pro-vided and approved and Technical Specifications to avoid operation in regions of potential thermal-hydraulic instability during single-loop operation.

Response

HCGS Draft Technical Specification Section 3/4.4.1, Recirculation System, prohibits single-loop operation. MP 85 64/07 4-mr

SER Technical Specification Issue No. 6 (SER Section 4.4.5) Crud Effects Crud deposition causes gradual flow reductions in some light-water-reactor cores. However, measurement of core flow by jet pump pressure drop and core plate pressure drop will provide adequato indication of such flow reductions, if they should occur. Technical Specifications will require 'that the core flow be checked at least once every 24 hours to detect flow reduction.

Response

HCGS Draft Technical Specification Section 4.4.1.2, Jet Pump Surveillance Requirements, provides the requirement that the core flow be checked at least once per 24 hours to detect flow reduction. P MP 85 64/07 5-mr L_

SER Technical Specification Issue No. 7 (SER Section 4.4.6) Loose Parts Monitoring System Channel Operability The staf f has reviewed the Hope Creek LPMS program. On the basis of the applicant's evaluation that the LPMS is in compliance with RG 1.133, the staff has concluded that the Hope Creek LPMS is acceptable on the condition that the Technical Specifications include appropriate limiting condi-tions for operation and surveillance requirements to demon-strate the operability of LPMS channels.

Response

HCGS Draft Technical Specification Sections 3.3.7.9 and 4.3.7.9, Loose-Part Detection System provides the appro-priate limiting conditions for operation and surveillance requirements to demonstrate the operability of LPMS channels. l l b MP 8!: 64/07 6-mr

r SER Technical Specification Issue No. 9 (SER Section 5.2.5) Reactor Coolant Pressure Boundary Leakage Rates The systems' testing and calibration frequency and capabil-ity during power operation of the plant will be in ac-cordance with the Standard Technical Specifications and, therefore, meet the guidelines of RG 1.45, Position C.8. The applicant has committed to specify the maximum allowable identified and unidentified leakage rates as 25 gpm and 5 gpm, respectively, in the Technical Specifications.

Thus, the guidelines of RG 1.45, Position C.9, are met.

There-fore, the staff concludes that the requirements of GDC 30, " Quality of Reactor Coolant Pressure Boundary," have been satisfied.

Response

HCGS Draft Technical Specification Section 3/4.4.3 Reector Coolant System Leakage, subsection 3.4.3.2 specifies the maximum allowable identified and unidentified leakage rates as 25 gpm and 5 gpm, respectively. MP 85 64/07 8-mr

SER Technical Specification Issue No. 10 (SER Section 5.4.6) Reactor Core Isolation Cooling Pump Testing l-l To protect the RCIC pump from overheating, the RCIC system contains a miniflow line that discharges into the suppres-l sion pool when the line to the reactor vessel is isolated. When there is enough flow to the vessel, a valve in the miniflow line automatically closes, thus directing all flow to the reactor. The RCIC system is protected against the effects of waterhammer when it starts by a jockey pump sys-tem that maintains the discharge piping filled up to the in-jection valve. A high point vent is provided, and the sys-tem will be checked at least once every 31 days to ensure that the lines are filled. The RCIC system includes a full flow test line with water return to the condensate storage tank for periodic testing. Technical Specifications will include a flow test at least every 92 days and a system functional test at least every 18 months. Testing includes simulated automat 3: actuation and verification of proper automatic valve position. Both tests will verify that the RCIC pump will develop a minimum flow of 600 gpm. ' Response: HCGS Draft Technical Specification 3/4.7.4, Reactor Core Isolation Cooling System, surveillance Requirement 4.7.4 l provides the above test requirements. t i 1 MP 85 64/07 9-mr I l I ,.,s. .-.__.,____3

.c-SER Technical Specification Issue No. 11 (SER Section 5.4.7) Residual Heat Removal System Pump Operability The NRC staff requires that (1) low pressure coolant injec-tion mode operability is verified every 31 days, (2) each pump is shown to start from the control room every 91 days, and (3) a system functional test is performed without re-quiring coolant injection into the reactor vessel every 18 months. This periodic testing is in conformance with the requirements of GDC 34 and 61 and should be addressed in the Technical Specifications.

Response

HCGS_ Draft Technical Specification Section 3/4.5.1, ECCS-Operating,-Surveillance Requirement 4.5.1 provides the above test requirements. MP 85 64/07 10-mr

7 SER Technical Specification Issue No. 14 (SER Section 6.2.3) Testing Of Inleakage Rate And Drawdown Time The applicant will verify the design inleakage rate and drawdown time by preoperational and periodic tests. The staff will include a requirement for these periodic tests in the Technical Specifications. It finds this analysis and test commitment to be in conformance with Branch Technical Position (BTP) CSB 6-3 and, therefore, acceptable.

Response

HCGS Draft Technical Specification Section'3/4.6.5 Reactor Building (Secondary Containment), Surveillance Requirement 4.6.5.1 provides the above test requirements. MP 85 64/07 11-mr

SER Technical Specification-Issue No. 21 (SER Section 6.5.1.3) water Seal Bucket Drain Tap Surveillance On the basis of its evaluation, the respect to the SRP criteria, the staff finds the proposed ESF atmosphere cleanup systems acceptable. The filter efficiencies given in Table 2 of RG 1.52 are appropriate for use in accident analyses. As one of the surveillance items for the ESF filter systems, the Technical Specifications will require that the water seal bucket drain traps be inspected for proper water level at 14-day intervals.

Response

k HCGS Draft Technical Specification Section 3/4.6.5.3, FRVS, has been revised to add the surveillance requirement for the drain traps. 5 M P85 64/09 l-mw

A e CONTAIM4ENT SYSTBtl D M. M_> $ 1 M_. k % '9 y A N D V D 8Tlk ATl* H LIMITING CCN0! TION FOR OPERATION ds $4 74,% reiw c. dab. wds e d AwoV9his vedt w shall be OPERA 8LE. 3.6.5.3 OPERATIdNAL CONDITIONS 1, 2, 3 and *. I APPLICA8ILITY: /0 kd , Fus vec.hadtkds co.ut.vws mt ::t r t : t ; i - inoperabte, rest 4.,e ACTION: f "~~~ inoperable :d:; t:.g 0PERA8LE status within 7 days, or: WithAene it " ?'; ::: a. In OPERATIONAL CONDITION 1, 2 or 3, be in a = i thefollowig within the next 12 hours and in COLD SHUTDO $I 1. sfJ nedter 6 M iuspendhandlingofirradiatedfuel.I .~ In Operationaldondition *, CORE ALTERATIONS and operations 2. in the7 x r t~r' =t ' r = l The with a potential :for draining the reactor v 3 wb& ved um.hinoperable in Opera yaNs nc.W1.%n With _,g etr?;' ;d handlino of irradiated fuel in the W Agn r t-nt rt :tyt hW% ""aining tde, CORE ALTERATION 3 o b. _n* Candi'ig M, suspen Y reactor vessel. ',,r Mare not applicable. SURVE!LLANCE REQUIREWENTS ved Msdemonstrated OPERABL a*4 %o Eacn :pe snr. FR. s reccedatie.r:t;; ;n trutrrt =r:y:t:- shall be u d flew 4,# At4 east once per 31 days by initiating, frem 4.o 3 ifyino that the through the HEPA filters and charcoal 4 0P(RA8LE.c v ad WQh h6% .b M br A 6. A g fj and durirg ertrj :rti_,the reactor vessel. Shen irractated ft.ei is being handled in theCORE i rH er-w e w A r M av ved H r~c-Awo n*Ansk'. v/ /tA sat o Ays AveKAr' rAn/s HRv4 A ss/A rfA..s GM. A r ste er *~e t I Any g..rA #eA A ro.*g s,ets d$ &f feLi o no c. f)fg yg g / ye yyg SAAL o vgxpro w, 7 d /ev. 3 j 3/4 s-iw f re me " ROPF C43.K

CONTAIPesENT SYSTEMS .s $UtVEILLAg g asanIREMENTS (Continued) At least once per 18 months or (1) after any structural maintenance C. E. on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the subsystem by: 1. Verifying that the, subsystem satisfies the in place penetration l and bypass leakage testing aceeptance criteria of less thant(15 l and uses the test procedure guidance in Regulatory Positions C.5.a.i C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2. March 1978, b-and the system flow rates h ( 200) ;f; : 11 are. So htso% %c.k FM5 vecicew\\ch uwA a,4 geoo eb,tw% be en, coo c. .ch we vev h A. 3 2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.h of Regulatory Guide 1.52, Revision 2 March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2 March 1978, 'l i for a methyl iodida penetration of less than f!ME; and l So,eco eb t iet, &c, k nys cedmeh et a4 9, coo Nzio% %,c eMite vek um,k l 3. Verifying a subsystem flow rate ofA(2200) ;f: : 1 5 during system operation when tested in accordance with ANSI N510-1975. dg. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than p. At least once per 18 months by: Ah cedrew\\o. Von. hbdvow.e d bss % w si* tbs %. e-.fr ^ N " *k at the pressure drop across the combined HEPA Verifyi 1. filters and charcoal adsorber banks is less than {88 inches *^ Water GaugeAwhile operating the filter train at a f1bw rate of '2:00; em ; = 3opeo eb t to% foc eu.h RMs rec.irewk%~ M I ad 3, coo eb 2 so% be ed VMS vest 4. 2. Verifying that the filter train starts and isolation dampers open on egch of the following test signals: Manual initiation from the control room, and s. b. Simulated automatic initiation signal. 2. rifyin; 2;t 2: f11' r ;;;1' ; t p::: 11;;r; ::n 5: ::=:Py 4-chweeweAb b d i .;; x:: :nd OM f;; ;;; :: x x:1ly :":-*:d. ed att N Tae e ved 3h. Verifying that the heaters dis'sipate h t kwlwhen tested dM lead in accordance with ANSI M510-1975. Aha verWg'M.eA33 conte.1 inO<wned s overde % %Ada,,4Wr-t C. RY _.. 3, kg 70?c A.5 tee.2 sm en-OC 20 C/0) 3/4 6-30 0

~ CCHTAINNENT SYSTEMS l SURVEILLMcE REQUIREMENTS (Continued) 4,. DoY ksct stretel ff After each comple e or partial replacement of a HEPA filter bank by verifying that th HEPA filter bank satisfies the inplace penetration .h in accordance hpw) B eakage testin acceptance criteria of less than @ low rate of (2000; 1 with ANSI M510-197 hile operating the system at a f f =' so,ooo eb T sot b each Fans vecivewWim 4 4 g, coo d. J tm% be each VRNs ved und.. After each complete or partial replacemant of a charcoal adsorber

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bank by verifying that the charcoal adsorber bank satisfies the inplace hrss*~ penetration anaMeakage testing acceptanc criteria of less than ('{PX j in accordance with ANSI H510-1975 for a h ogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of w. .,_. So, coo ek tic % fue eac.K F9Ns vecieew\\.km Q aed 9, coo eb tioY. b ed van ved mA. cfWicir*~ey gets : End:vidal Fevs ese:enul bik 4d vent ca.uc.oel C:ller-is 95%. sin << C:l&e. s a.re-i.e cer t * *

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( T~ --!.;; _;;11:31; he. ; ;;;fA filt;r ;r ;%;r;;;l ed;;.-:;;r eff'-i.T;y efficiency of 99% used, or 15 when a HEPA filter or charcoal ads of 95% or less sumed in the NRC staff's safety ation. (Use the value assumed for the cal adsorber effi if the value for the HEPA filter is different f che adsorber efficiency in the staff's safety evaluation.)) (**0.175% value a le when a charcoal adshf'b iciency of 99% is 'assumsd. value applicable when a charcoal adsorbe iciency of assumed, or 10% value applicable when a charcoal adso

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SER Technical Spec,ification Issue No. 30 (SER Section 8.3.1.3) Diesel Generator Connected Loads Surveillance Requirements for periodic verification that automatically connected loads do not exceed the continuous rating of the diesel generator will be included in the -Technical Specifications.

Response

HCGS Draft Technical Specification Section 3/4.8.1, A.C. Sources, Surveillance Requirement 4.8.1.1.2.h.9 provides the above test requirement to verify that the auto-connected loads to each diesel generator do not exceed the 2000-hour rating of 4737 kW, at least once per 18 months, during shutdown. MP 85 64/07 12-mr

j SER Technical Specification Issue No. 31 (SER Section 8.3.1.7) Load Sequencer Logic Surveillance requirements for the operability of the load sequencer logic on a 30-day periodic basis will be included in the Technical Specifications.

Response

HCGS Draft Technical Specification Section 3/4.8.1, A.C. Sources, Surveillance Requirement 4.8.1.1.2.e provides the above test requirement to perform a functional test on the emergency load sequencer to verify operability at least once per 31 days. MP 85 64/07 13-mr

SER Technical Specification Issue No. 32 (SER Section 8.3.2.7) DC System Monitoring The staff has concluded that the above-cited monitoring, augmented by the periodic test and surveillance requirements that are included in the Technical Specifications, provides reasonable assurance that the Class lE dc power system is ready to perform its intended safety function.

Response

HCGS Draft Technical Specification Section 4.8.2.1, D.C. Sources - Operating, provides the surveillance requirements which assure that the Class 1E de power system is ready to perform its intended safety function. 4 MP 85 64/07 14-mr

E SER Technical Specification Issue No. 34 (SER Section 873.3.4.1) Periodic System Testing Periodic system tests shall be performed using written pro-cedures which will be designed to demonstrate system per-formance. The frequency of testing shall be governed by the frequencies specified in the Technical Specifications. The following periodic system tests are required by Section 6.4 of IEEE Std. 308-1974 to demonstrate the following: (1) The Class lE loads can operate on the preferred power supply. .(2) The loss of the preferred power supply can be detected. (3) The standby power supply can be started and can accept design load within the design-basis time. (4) The standby power supply is independent of the preferred power supply. In a letter dated September 21, 1984, the applicant stated that each of these tests would be included in the Hope Creek Technical Specifications. On the basis of this statement, the staff concludes that periodic system testing will comply with the guidelines of Section 6.4 of IEEE Std. 308-1974, meets the requirements of GDC 17 and 18, and is acceptable. Inclusion of the subject specifications will be reviewed with the Technical Specifications.

Response

HCGS Draft Technical Specification Section 3/4.8.1 A.C. Sources, Surveillance Requirement 4.8.1.1.2 provides the above test requirements. MP 85 64/07 15-mr

SER Technical Specification Issue No. 35 (SER Section

8. 3. 3. 4. 2)

Load Sequencer Testing In Amendment 4 to the FSAR, the applicant, in response to a request for information, indicated that provisions exist for testing the automatic load sequencer logic for various modes during normal plant operation. If an actual loss of offsite power or accident signal occurs during testing, the se-quencer resets automatically and responds to the signal. This design meets the guidelines of.RG 1.118 and the re-quirements of GDC 18 and is acceptable. Periodic testing of the load sequencer will be included in the Hope Creek Technical Specifications.

Response

HCGS Draft Technical Specification Section 3/4.8.1, A.C. Sources, Surveillance Requirement 4.8.1.1.2, Items e, h.4 and h.6 provide the above requirements for load sequencer testing. MP 85 64/07 16-mr

SER Technical Specification Issue No. 36 (SER Section 8.3.3.5.4) Testing of Fuses' Subsequently, in a letter dated August 1, 1984, the appli-cant stated that testing of fuses will be done at least once every 18 months using the provisions specified in the Stand-ard Technical Specifications. On the basis of this statement, the staff considers this item resolved.

Response

HCGS Draft Technical Specification Section 3/4.8.4, Electri-cal Equipment Protective Devices, Surveillance Requirement 4.8.4.1, Item 3 provides the above test requirement for fuses, at least once per 18 months. MP 85 64/07 17-mr

SER Technical Specification Issue No. 38 (SER Section 9.2.1) Station Service Water Pump Testing The SSW pumps are normally operating. The' availability of the standby pumps is ensured by periodic functional tests and. inspections. The system design also incorporates pro-visions for accessibility to permit inservice inspection a9 required. The frequency of the functional _ testing and tr - spection will be in accordance with the Standard Technical Specifications. Thus, the staff concludes that the requirements of GDC 45 and 46 are satisfied.

Response

HCGS Draft Technical Specification Section 3/4.7.1, Service Water Systems, Surveillance Requirement 4.7.1.2, and Sur-veillance Requirement 4.0.5 provide the above requirements for functional testing and inspection of the service water pumps. MP 85 64/07 18-mr

SER Technical Specification Issue No. 39 (SER Section 9.2.2) Safety Auxiliaries Cooling System And.% factor Auxiliaries Cooling System Pump Availability The SACS and RACS pumps are normally operating. The availability of punps are on standby is ensured by periodic functional tests and inspections as delineated in the plant Technical Specifications. The system design also incor-porates provisions for accessibility to permit inservice inspection as required. Thus, the staff concludes that the requirements of GDC 45 and 46 are satisfied.

Response

HCGS Draft Technical Specification Section 3/4.7.1, Service Water System, Surveillance Requirements 4.7.1.1, and Sur-veillance Requirement 4.0.5 provide the above requirements for functional testing and inspection of the SACS pumps. As . stated in FSAR Section 9.2.8.3, the RACS has no safety-related function and is not required to be operable follow-ing a LOCA. Therefore, Technical Specifications for the RACS pumps are not required. MP 85 64/07 19-mr

SER Technical Specification Issue No. 44 (SER Section 9.5.1.5) Fire Watch The Class B system is electrically supervised to detect circuit breaks, ground faults, removal of a detection device from a detector circuit, and power failure. If any of these problems occur, fire detection system trouble.is annunciated locally and in the main control room. This would alert the oeprators to repair the system or establish a fire watch in the affected area in conformance with the plant Technical Specifications. The staff concludes that the possibility of the Class B supervised portion of-the detection system being inoperable for an extended time is low and can accept this as a deviation to its guidelines.

Response

HCGS Draft Technical Specification Section 3.3.7.8 provides the above requirement to restore the system to operable status or establish a fire watch in the affected areas. 8 MP 85 64/07 21-mr

F I SER Technical Specification Issue No. 45 (SER Section 10.2) l Turbine Steam Valve Inspection i An inservice inspection program for the main steam stop and control valves and corabined intercept valves is provided and includes: 1. -dismantling and inspecting one of each type of turbine steam valve;at approximately 3-1/3 year. intervals during L refueling or maintenance shutdowns coinciding with the l inservice inspection schedule. L 2. exercising and' observing at least once a week the main steam stop and control valves and combine intercept valves. This program will be included in the plant Technical Specifications.

Response

l: HCGS Draft Technical Specification Section 3/4.3.8, Turbine Overspeed Protection System, Surveillance Requirement 4.3.8.2 a.1 and a.2 provide the requirement to exercise and < observe the main steam stop valves and combined intercept valves at least once per 7 days. I Surveillance Requirement 4.3.8.2' b provides !the requirement to exercise and observe the high pressure turbine control valves at least once per 31 days. This change to the BWR [ Standard Technical Specification-(i.e., allowing the high-pressure turbine control valves to be tested monthly rather than weekly) is based on_ General Electric Technical Informa-tion Letter (TIL) No. 969 which concludes that the excellent reliability record of these valves justifies this change in-the frequency of-surveillance testing. HCGS FSAR 10.2.3 is being revised in Amendment 10 to reflect the above revision i to the surveillance. testing of the high pressure turbine control valves. Surveillance Requirement 4.3.8.2 d provides the requirement I to-dismantle and inspect one of each type of turbine steam valve at least-once per 40 months. l -MP 85 64/07 22-mr lu ['

SER Technical Specification Issue No. 46 (SER Section 10.4.4) Turbine Bypass Valve Surveillance The applicant in a letter dated August 1, 1984, stated that the turbine bypass valves would be exercised at least once a week, that a turbine bypass system functional test, whicn includes a simulated automatic actis tion and verification ~ that each automatic valve actuates to its correct position, would be performed every 18 months; and that this would be included in the plant Technical Specifications.

Response

HCGS Draft Technical Specification Section 3/4.7.10, Main Turbine Bypass System, Surveillance Requirement 4.7.10a provides the requirement to exercise each turbine bypass valve at least once per 31 days. This change to the BWR Standard Technical Specification (i.e., allowing the turbine bypass valves to be tested monthly rather than weekly) is based on General Electric Service Information Letter (SIL) No. 413 which concludes tha t the excellent reliability record of thes'e valves justifies this change.in the frequency of surveillance testing. The response to FSAR Question 430.167 is being revised in Amendment 10 to reflect the above revision to the surveillance testing of the turbine bypass valves. Surveillance Requirement 4.7.10 b.1 provides the requirement to perform a turbine bypass system functional test which in-cludes a simulated automatic activation and verification that each automatic valve actuates to its correct position, at least once per 18 months. MP 85 64/07 23-mr'

SER Technical Specification Issue No. 50 (SER Section 15.6.4) MSIV Closure Time A guillotine break of one of the four main steamlines is postulated to occur outside the primary containment, down-stream of the outermost isolation valve, resulting in mass loss of both ends of the break. The primary coolant loss is assumed to be limited by steamline flow limiters to a maxi-mum release rate of 200 percent of rated steam flow, and by Technical Specifications which ensure the maximum closure time of the main steam isolation valves (MSIVs) is 5.5 sec. Mass loss from the broken steamline terminates when the MSIVs are fully closed. The applicant has calculated that 99,400 lb. of water and steam would be released to the atmosphere before the MSIVs would close following such an accident. The staff followed the recommendation of SRP Section 15.6.4 (NUREG-0800) and conservatively assumed 140,000 lb. of coolant would be released.

Response

HCGS Draft Technical Specification Section 3/4.4.7, Main Steam Isolation Valves, provides the limiting conditions for operation and surveillance requirements for the MSIVs. The maximum closure time specified is 5 seconds. DJD: vw MP85 76 04 1-vw

SER Technical Specification Issue No. 51 (SER Section 15.9.3) SRV Failure Reporting Because Hope Creek has not yet operated, no valve failures have been reported. The applicant will promptly report safety / relief valve failures via the Licensee Event Report system and will summarize failures in the annual report. The plant Technical Specifications will require these fail-ures to be reported within 30 days. The staff finds this acceptable.

Response

HCGS Draft Technical Specification Section 6.6.1, Reportable Event Action, provide the above requirement to report safety / relief valve failures within 30 days, in accordance with 10 CFR 50.73. HCGS Draft Technical Specification Section 6.9.1.5, Annual Reports, provides the requirement to document all challenges to main steam safety / relief valves in the annual report. b' MP 85 64/07 24-mr

l t ATTACHMENT 4 Revision 3 HCGS Draft Technical Specification Pages l l l l l t

l 6 Y t i a-HOPE CREEK GDlIRATING STATICit i .w. 3 DRAFT TECHNICAL SPECIFICATICNS 6 1EOeGGA H PEBIPM M MIE 5ERAHbEffRN N (5 485) m 1 -e-w-w w-- w-m ee -w n----,m--- ---v~-w--------,-

i-1 l 4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers Index 0 1 2 ii 2 iii 0 iv 0 v 0 vi 0 vii 0 viii 0 ix 0 x 0 xi 2 xii 0 xiii 0 xiv 0 xv 0 xvi 0 xvii 0 xviii 0 xix 0 xx 0 xxi 0 Section 1.0 0 1-1 0 1-2 0 1-3 2 Insert A to pg. 1-3 2 1-4 2 Insert A to pg. 1-4 2 Insert B to pg. 1-4 2 Insert C to pg. 1-4 2 1-5 2 Insert A to pg. 1-5 2 1-6 2 Insert A to pg. 1-6 2 Insert B to pg. 1-6 2 1-7 2 Insert A to pg. 1-7 2 1-8 2 1-9 0 Section 2.0 0 2-1 0 2-2 0 2-3 0 2-4 0 Bases for Section 2.0 0 Note 0 MP85 20/09 l-db Rev. 3

4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers B2-1 0 B2-2 0 B2-3 0 B2-4 0 B2-5 0 B2-6 0 B2-7 0 B2-8 0 B2-9 0 Section 3.0 & 4.0 0 3/4 0-1 0 Insert A to pg. 3/4 0-1 0 3/4 0-2 0 3/4 0-3 0 3/4 1-1 0 3/4 1-2 0 3/4.1-3 0 3/4 1-4 0 3/4 1-5 0 3/4 1-6 0 3/4 1-7 0 3/4 1-8 0 3/4 1-9 0 Insert to pg. 3/4 1-9 0 3/4 1-10 0 3/4 1-11 0 3/4 1-12 0 3/4 1-13 0 3/4 1-14 0 3/4 1-15 0 3/4 1-16 0 3/4 1-17 0 3/4 1-18 0 3/4 1-19 0 3/4 1-20 0 3/4 1-21 0 3/4 2-1 0 3/4 2-2 0 3/4 2-3 0 3/4 2-4 0 3/4 2-5 0 MP85 20/09 2-db Rev. 3

4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS -LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 2-6 0 3/4 3-1 0 3/4 3-2 0 3/4.3-3 0 3/4 3-4 0 3/4 3-5 0 3/4 3-7 0 3/4 3-8 0 3/4 3-9 0 3/4 3-10 0 3/4 3-11 0 ' 3/4 3-12 0 3/4 3-13 0 3/4 3-14 0 3/4 3-15 0 3/4 3-16 0 3/4 3-17 0 3/4 3-18 0 3/4 3-19 0 3/4 3-20 0 3/4 3-21 0 3/4 3-22 0 3/4 3-23 0 3/4 3-24 0 3/4 3-25 0 3/4 3-26 0 3/4 3-27 0 3/4 3-28 0 3/4 3-29 0 i - 3/4 3-30 0 3/4 3-31 0 3/4 3-32 0 3/4 3-33 0 3/4 3-34 0 3/4 3-35 0 3/4 3-36 0 3/4.3-37 0 Insert A to O page 3/4 3-37 3/4 3-38 0 3/4 3-39 0 -MP85 20/09 3-db Rev. 3 -~r --p q +,,e-+- p mv-

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• Revision Pages Numbers 3/4 3-40 0

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4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 3-81 0 3/4 3-82 0 3/4 3-83 0 3/4 3-84 0 3/4 3-85 0 3/4 3-86 0 Insert to pg. 3/4 3-86 1 3/4 3-87 0 3/4 3-88 0 3/4 3-89 0 3/4 3-90 0 3/4 3-91 0 3/4 3-92 0 3/4 3-93 0 3/4 3-94 0 3/4 3-95 0 3/4 3-96 0 3/4 3-97 0 3/4 3-98 0 3/4 3-99 0 3/4 3-100 0 3/4 3-101 0 3/4 3-102 0 3/4 3-103 0 3/4 3-104 0 3/4 3-105 0 3/4 3-106 0 3/4 3-107 0 3/4 3-108 0 3/4 3-109 0 3/4 3-110 0 3/4 3-111 0 3/4 3-112 0 3/4 3-113 0 3/4 3-114 0 3/4 4-1 0 3/4 4-2 0 3/4 4-3 0 3/4 4-4 1 3/4 4-5 0 3/4 4-6 0 MP85 20/09 5-db Rev. 3

4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4.4-7 0 Insert A&B to O page 3/4 4-7 3/4 4-8 0 3/4 4-9 0 3/4 4-10 0 3/4 4-11 0 3/4 4-12 0 3/4 4-13 0 3/4 4-14 0 3/4 4-15 0 3/4 4-16 0 3/4 4-17 0 3/4 4-18 0 3/4 4-19 0 3/4 4-20 0 3/4 4-21 0 3/4 4-22 0 3/4 4-23 0 3/4 4-24 0 .3/4 4-25 0 Insert B&C to 0 page 3/4 4-25 3/4 4-26 0 3/4 4-27 0 3/4 4-28 0 3/4 5-1 0 3/4 5-2 0 3/4 5-3 0 3/4 5-4 0 3/4 5-5 0 3/4 5-6 0 3/4 5-7 0 3/4 5-8 0 3/4 5-9 0 3/4 6-1 0 3/4 6-2 0 3/4 6-3 0 3/4 6-4 0 3/4 6-5 0 3/4 6-6 0 r MP85 20/09 6-db Rev. 3

i ) 4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 6-7 0 3/4 6-8 1 Insert A to pg. 3/4 6-8 1 Insert B to pg. 3/4 6-8 1 Insert C to pg. 3/4 6-8 1 3/4 6-9 0 3/4 6-10 1 3/4 6-11 1 3/4 6-11a 1 3/4 6-11b 1 3/4 6-11c 1 3/4 6-11d 1 3/4 6-lle 1 3/4 6-11f 1 3/4 6-11g 1 3/4 6-12 1 3/4 6-13 0 3/4 6-14 0 Insert A&B to 0 page 3/4 6-14 3/4 6-15 0 Insert to pg. 3/4 6-15 0 3/4 6-16 0 3/4 6-17 0 3/4 6-18 1 Insert A&B to 1 page 3/4 6-18 3/4 6-19 0 3/4 6-20 0 Insert A&B to O page 3/4 6-20 3/4 6-21 0 3/4 6-22 0 3/4 6-23 0 3/4 6-24 0 3/4 6-25 0 3/4 6-26 0 3/4 6-27 0 3/4 6-28 0 3/4 6-29 0 3/4 6-30 0 .MP85 20/09 7-db Rev. 3

4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 6-31 1 3/4 6-32 0 3/4 6-33 0 3/4 6-34 0 3/4 6-35 0 3/4 6-36. 0 3/4 6-37 1 3/4 6-38 0 3/4 6-39 1 3/4 6-40 1 3/4 6-41 0 3/4 6-42 1 3/4 6-43 0 3/4 6-44 0 3/4 6-45 0 3/4 6-46 0 Insert A to pg. 3/4 6-46 0 3/4 6-47. 0 3/4 6-48 0 3/4 6-49 3 3/4 6-50 3 3/4 6-51 3 3/4 6-52 1 Insert A to 1 page 3/4 6-52 3/4 6-53 0 3/4 7-1 0 3/4 7-2 0 Insert E&F to O page 3/4 7-2 3/4 7-3 0 Insert to pg. 3/4 7-3 0 3/4 7-4 0 3/4 7-5 3 Insert A'to pg. 3/4 7-5 3 3/4 7-6 0 3/4 7-7' 0 3/4 7-8 0 3/4 7-9 0 3/4 7-10 0 3/4 7-11 0 .MP85 20/09 8-db Rev. 3

n 4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4.7-12 0 3/4 7-13 0 3/4 7-14 0 Insert B&C to O page 3/4 7-14 3/4 7-15 0 Insert D to pg. 3/4 7-15 0 3/4 7-16 0 3/4 7-17 0 3/4 7-18 0 3/4 7-19 0 3/4 7-20 1 3/4 7-21 1 3/4 7-22 0 3/4 7-23 1 Insert to pg. 3/4 7-23 0 3/4 7-24 0 3/4 7-25 1 Insert to pg. 3/4 7-25 0 3/4 7-26 1 Insert to pg. 3/4 7-26 1 3/4 7-27 1 Insert to pg. 3/4 7-27 1 3/4 7-28 1 Insert A&B to page 1 3/4 7-28 3/4 7-29 0 3/4 8-1 0 Insert A to pg. 3/4 8-1 0 Insert B to pg. 3/4 8-1 0 3/4 8-2 0 Insert to pg. 3/4 8-2 0 3/4 8-3 0 Insert to pg. 3/4 8-3 0 3/4 8-4 0 3/4 8-5 0 Notes to pg. 3/4 8-5 0 3/4 8-6 0 3/4 8-7 0 3/4 8-8 0 Insert A to pg. 3/4 8-8 0 MP85 20/09 9-db Rev. 3

4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 8-9 0 Insert A to pg. 3/4 8-9 0 Insert B to pg. 3/4 8-9 0 3/4 8-10 0 Insert A to pg. 3/4 8-10 0 Insert B to pg. 3/4 8-10 0 3/4 8-11 0 3/4 8-12 0 Insert to pg. 3/4 8-12 0 3/4 8-13 0 Insert to pg. 3/4 8-13 0 3/4 8-14 0 Insert to op. 3/4 8-14 0 3/4 8-15 0 3/4 8-16 0 3/4 8-17 0 3/4 8-18 0 Insert to pg. 3/4 8-18 0 3/4 8-19 0 3/4 8-20 Sheet 1 0 3/4 8-20 Sheet 2 0 3/4 8-20 Sheet 3 0 3/4 8-20 sheet 4 0 3/4 8-20 Sheet.5 0 3/4 8-20 Sheet 6 0 3/4 8-20 Sheet 7 0 3/4 8-21 0 3/4 8-22 Sheet 1 0 3/4 8-22 Sheet 2 0 3/4 8-22 Sheet 3 0 3/4 8-22 Sheet 4 0 3/4 8-22 Sheet 5 0 3~/4 8-23 0 3/4 9-1 0 3/4 9-2 0 3/4 9-3 0 3/4 9-4 0 3/4 9-5 0 i 3/4 9-6 0 3/4 9-7 0 3/4 9-8 0 MP85 20/09 10-db Rev. 3 c

4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 9-9 0 3/4 9-10 0 3/4 9-11 0 3/4 9-12 0 3/4 9-13 0 3/4 9-14 0 3/4 9-15 0 3/4 9-16 0 3/4 9-17 0 3/4 10-1 0 3/4 10-2 0 3/4 10-3 0 3/4 10-4 0 3/4 10-5 0 3/4 10-6 0 3/4 11-1 2 3/4 11-2 2 3/4 11-3 2 3/4 11-4 2 3/4 11-5 2 3/4 11-6 2 3/4 11-7 2 3/4 11-8 2 3/4 11-9 2 3/4 11-10 2 3/4 11-11 2 3/4 11-12 2 Insert A to pg. 3/4 11-12 2 3/4 11-13 2 3/4 11-14 2 3/4 11-15 2 3/4 11-16 2 3/4 11-17 2 -3/4 11-18 2 Insert A&B to pg. 3/4 11-18 2 3/4 11-19 2 3/4 11-20 2 3/4 11-21 2 3/4 12-1 2 3/4 12-2 2 MP85 20/09 11-db Rev. 3

I-4/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision 'Pages Numbers 3/4 12-3 2 3/4 12-4 2 3/4 12-5 2 3/4 12-6 2 3/4 12-7 2 3/4 12-8 2 3/4 12-9 2 3/4 12-10 2 3/4 12-11 2 3/4 12-12 2 3/4 12-13 2 3/4 12-14 2 Bases for Section 3.0 and 4.0 0 Note to pg. B3.0&4.0 0 B3/4 0-1 0 B3/4 0-2 0 B3/4 0-3 0 B3/4 1-1 0 B3/4 1-2 0 Insert.A to pg. B3/4 1-2 0 B3/4 1-3 0 B3/4 1-4 0 Insert to pg. B3/4 1-4 0 B3/4 2-1 0 B3/4 2-2 0 B3/4 2-3 0 B3/4 2-4 0 B3/4 2-5 0 B3/4 3-1 0 B3/4 3-2 0 B3/4 3-3 0 B'3/4 3-4 0 B3/4 3-5 0 B3/4 3-6 0 Insert to pg. B3/4 3-6 0 B3/4 3-7 0 B3/4 4-1 0 E Insert B to pg. B3/4 4-1 0 B3/4 4-2 0 t B3/4 4-3 0 f ~ MP85 20/09 12-db Rev. 3

r,. 3 4/85 yf, HOPE CREEK GENERATING STATION i DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision j Pages . Numbers B3/4 4-4 0 6 s Insert to pg. B3/4 4-4 0 B3/4 4-5 0 Insert A to pg. B3/4 4-5 0 B3/4 4-6 0 B3/4 4-7 0 B3/4 4-8 0 B3/4 5,-1 0 B3/4 5-2 0 B3/4 6-1 0 Insert to pgi B3/4 6-1 0 B3/4 6-2 0 183/4 6-3 0 B3/4 6-4 0 B3/4 6-5 0 Insert to pg. B3/4 6-5 0 B3/4 6-6 f 0 B3/4 7-1 O B3/4 7-2 1 0 Insert to pg. B3/4 7-2 0 B3/4 7-3 0 s' B3/4 7-4 0' Insert to pg. B3/4 7-4 0 s / B3/4 7-5 0 B3/4 8-1 0 B3/4 8-2 0 B3/4 8-3 0 B3/4 9-1 0 B3/4 9-2 0 B3/4 10-1 0 + B3/4 11-1 2 B3/4 11-2 2 B3/4 11-3 2 B3/4 11-4 2 B3/4 11-5 2 B3/4 11-6 2 B3/4 12-1 2 B3/4 12-2 2 Section 5.0 0 5-1 0 5-2 0 e MP85 20/09 13-db! Rev. 3

f 4/85 HOPE' CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 5-3 0 5-4 0 5-5 0 5-6 0 Section 6.0 0 6-1 0 2 0 6-3 0 6-4 0 6-5 0 6-6 0 6-7 0 6 0 6-9 0 6-10 0 6 0 6-12 0 6-13 0 6-14' 0 6-15 0 6-16 0 6-17 0 6-18 0 6-19 0 Insert A,B&C to O page 6-19 6-20 0 6-21 0 6-22 0 6-23 0 6-24 0 6-25 0 6-26 0 Insert B to pg. 6-26 0 6-27 0 6-28 0 6-29 0 MP85 20/09 14-db Rev. 3

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• p are not appitcable.

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CONTAINMENT SYSTEMS SURVEIt.t.A M REQUIREMENTS (Continued) At least once per 18 months or (1) after any structural maintenance C. x on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire o. chemical release in any ventilation zone connunicating with the subsystem by: 1. Verifying that the, subsystem satisfies the in-place penetration I and bypass leakage testing acceptance criteria of less than1@ l and uses the test procedure guidance in Regulatory Positions C.5.a t C.S.c and C.5.d of Regulatory Guide 1.52, Revision 2. March 1978, b-and the system flow ratasu (0 00) ;f; ; 15. an 3c,ooo dmtso=4 to'ch FM5 Mc.Wcw\\cJthm.wwA aw& goco eb.tto% be ecu.k no yeh,ch. 3 2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.h of Regulatory Guide 1.52, Revision 2 March 1978, meets the laboratory testing criteria of Regulatory t Position C.6.a of Regulatory Guide 1.52 Revision 2, March 1978, ,l i so, coo cha e iot.4c,=L.Vavs c chwhb.W!t a 4 9,cco(b@rio% for a methyl iodide penetration of less than

and 3.

Verifying a subsystem flow rate of'(0:00) :f: : 7 5 during system operation when tasted in accordance with ANSI N510-1975. dg. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbor, sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a i l of Regulatory Guide 1.52, Revision 2. March 1978, for a methyl fodida penetration of less than p%. At least once per 18 months by b.k % cec.icew\\o. oA kWw %w.c%1\\en b 5'm c6 k%. c.Jf at the pressure drop across the combined HEPA Verifyi 1. filters and charcoal adsorber banks is less than (88 inches **" Water GaugeAwhile operating the filter train at a fibw rate of ' 000).% ; ;;".3o,*oo eb t to% Sc m.h FM5 rec.irewh M o.wd %,000 d w 210 % be Cath M S Me.d Etk. 2. Verifying that the filter train starts and isolation dampers open on egch of the following test signals: Manual initiation from the control room, and a. b. Staulated automatic initiation signal.

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;rifyi q C;t 2: filter ; ni'n; ty;;:: Z :n ::: t: for uc.k eeneeOEsa uaA

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ua 32 uw T.c e=A ved. Bh. Verifying that the heaters dis'sipate b 2 h kwlwhen tested d.9\\ toad in accordance with ANSI N510-1975;Msa vecLj$'Waa&h coded Mdeswh opwde b %dc%'., : -., =", .. 2. " Yo f70fe A. h

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• o CONTAINMENT SYSTEMS SURVEILI.MCE REQUIREMENTS (Continued) 4e a. Dor kset ste***l ff After each comple e or partial replacement of a HEPA filter bank by verifying that th HEPA filter bank satisfies the inplace penetration hpW68Meekage testin acceptance criteria of less than q)5 in accordance h

with ANSI N510-197 11e operating the systes at a flow rate of (0:00;- eb Ttot 4=c each FUNs new-ca.km M m4 g,ooo d% /

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? 5. 30,000 e so m _ w v w s. a a.

After each complete or partial replacement of a charcoal adsorber

3. /.

bank by verifying that the charcoal adsorber bank satisfies the inplace hFpenetration aneMeakage testing acceptance criteria of less than q)5 in accordance with ANSI M510-1975 for a h5ogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of (^^,^,^) ef; ; 15. So, coo dm %s% %e e c.k VeNs teclec.w\\.km gg ad 9, coo eb toy. 6 e 4 v u s ye,A m A. gots : t,.tlvu al Fev s ese:en J bi k 4 4 ves t crueo./ C:Iber ef$eireey l e'** * # **vs e //>'< /*aes / 43 est siace des. c.M.. s a.re-3. <=i.. l is 44% l o ( "O^ s;h.; g;";;th.'.;.. ; :::TA f'It:r ;r :..;r;;;l ed;;rt;r ;ff'-!.T;y efficiency of 995 used, or 15 when a HEPA filter or charcoal ads of 955 or less sumed in the NRC staff's safet ation. (Use the l value assumed for the cal adsorter effi if the value for the HEPA filter is different f che adsorber efficiency in the staff's safety evaluation.)) (**0.1755 value a le when a charcoal adsbeb iciency of 995 is value applicable when a charcoal adsorbe iciency of assumedassumed, or 105 value applicable when a charcoal adso

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PLANT SYSTEMS. ULTIMATE HEAT SINK (0;;;i.ad) LIMITING CONDITIOM FOR OPERATION

3. 7.1. 3 The(ultimateheatsink)shallbeOPERABLEwith:

river A minimum (5::in) water level at or above elevation $76 ) m [ a. ,"46GG. datum, and 90.5 An average ([:'55) water temperature of less than or equal to g }*F. l / b. ~ (c. (.^t !:::t) (Tr:) 0*E."_^"'_E :::!' ; t: :-- *: :. ) l APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and *. l ACTION: With the requirements of the above specification not satisfied: a. In OPERATIONAL CONDITIONS 1, 2 or 3, be in at least HOT SHUT 00WN within 12 hours and in COLD SHUT 00WN within the next 24 hours. l SACS b. In OPERATIONAL CONDITIONS 4 or 5, declare the-ENA6W. system and the plant service water system inoperable and take the ACTION required s by Specification 3.7.1.1 and 3.7.1.2. In Operational Condition *, declare the plant service water system c. inoperable and take the ACTION required by Specification 3.7.1.2. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS I

4...

The { ultimate heat sink) shall be determined OPERABLE at least on IMsGLT river g a. 24 hours rifying the average (;,..ia) water te ure and water level to hin their limits. a 2_.._ m. .. 6... -..__,..,___........i.. TL ',..:_. :L. ::. ' 7. "EZ......N... _. '::. 7 s '"' "" ~ ' ~ ~ ~ I! (c. 1 : ."_. Z:.t'-, v:H fy h-th:t :::5 (p!::t r 5:: u:...) A !'"; ........___.4..n.. +__.u. r., 4,. -wed)'IS:h'Ib'I-ItfisEE.l 4.. 2 ,_A.c wa %c.22Et.% ~- % &. l 0.. "When handling irradiated fuel in the ;;:: CO:rj :: t .,h.e _9,E,,c.R.E.r.e.w. e.....s.-...m., 3/4 7-5 g,,, 3

LJn D D (* O D D tr (* D h3 O O A 'T' T hir* C* *T9 A 8T5 7 rsks e t usv&T A_ To _ f6 3lY 7 #3~ ._ 4.1. L 3.. _The _. ul b de._ b e aksi n c_ sMl__ k Meb med__ dfEEAO LE_.

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. _._. _ cis laws: .. _ _ _. - _ _ _.. - _.. _ c a, By veAtfpq af. least_. oue pse_2C hours. tkaf._. ctver. watn.\\eatl_ nu. cb or a Le tkL. _. m i niciu m li mit. y venfywy rnver_ waker.heapakmaastG.uly ___-.. Jo => t s._.. sa

1) Atleast enco pm.M hooct_ WIk_ aueA._du 4 cmp.ube im h equaltaas*A z) At leas 4 once p 4. 4 Lourc. uth _. rim wde

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