ML20128B963
| ML20128B963 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek |
| Issue date: | 07/01/1985 |
| From: | Mittl R Public Service Electric & Gas Co of New Jersey |
| To: | Butler W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20128B966 | List: |
| References | |
| NUDOCS 8507030400 | |
| Download: ML20128B963 (31) | |
Text
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Pubhc Sennce Electnc and Gas Company 80 Park Plaza, Newark, NJ 07101/ 201430 8217 MAILING ADDRESS / P.O. Bm 570, NewA, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation July 1, 1985 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Ge ntleme n:
SAFETY EVALUATION REPORT OPEN AND CONFIRMATORY ITEM STATUS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 is a current list which provides a status of the open and confirmatory items identified in Sections 1.7 and 1.8 of the Safety Evaluation Report (SER).
Items iden-tified 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 otherwise.
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 description of the issue which remains to be resolved.
Enclosed for your review and approval (see Attachment 3) are the resolutions to the SER items listed in Attachment 2.
This information will be incorporated, as required, into Amendment 12 of the HCGS FSAR.
Should you have any questions or require any additional information on these items, please contact us.
Very truly yours, 8507030400 850701
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Director of Nuclear Reactor Regulation 2
7/1/85 C
D. H. Wagner USNRC Licensing Project Manager (w/ attach.)
A.
R.
Blough USNRC Senior Resident Inspector (w/ attach.)
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Date 7/1/85 ATTACHMENT 1 R.
L. Mittl to A. Schwencer Itcm No.
Subject Status ltr. dated 01-1 Riverborne Missiles Comp'le ted 1/31/85, 2/22/85, 5/8/85 OI-2 Equipment Qualification Partial Response 2/1/85, 2/20/85, 2/28/85, 3/1/85, 6/11/85, 6/6/85, 6/25/85 (2),
6/28/85 01-3 Preservice Inspection Program Partial Response 2/14/85 & 3/19/85 OI-4 GDC 51 Compliance Completed 3/12/85 OI-5 Solid-State Logic Modules Partial Response 6/5/85 OI-6 Postaccident Monitoring Completed 5/14/85 Instrumentation OI-7 Minimum Separation Between Partial Response 4/4/85-Non-Class IE' Conduit and Class IE Cable Trays
'OI-8 Control of Heavy Loads Closed 1/18/85 (SSER 1) 01-9 Alternate and Safe Shutdown NRC Action 01-10 Delivery of Diesel Generator Closed Amendment 8 Fuel Oil and Lube Oil (SSER 1) 01-11 Filling of Key Management Open Positions 01-12 Training Program Items (a)
Initial Training Program Completed 1/7/85 (b)
Requalification Training Completed 12/28/84, 4/26/85 Program (Revised Program)
(c)
Replacement Training Completed 1/7/85 Program (d)
TMI I ssue s I. A. 2.1, Completed 1/7/85 I.A.3.1, and II.B.4 (e)
Nonlicensed Training Completed 1/7/85 Program 01-13 Emergency Dose Assessment Completed 1/7/85 Computer Model M P85 27/10 1-mr
2 R.
L.
Mittl to A.
Schwencer Item No.
Subject Status ltr. dated OI-14 Procedures Generation Package Partial Response 1/28/85 & 4/10/85 OI-15 Human Factors Engineering Partial Response 4/10/85 C-1 Feedwater Isolation Check Open Valve Analysis C-2 Plant-unique Analysis Report Completed 1/8/85 & 1/31/85 C-3 Inservice Testing of Pumps and Open Valves C-4 Fuel Assembly Accelerations Completed Amendment 8 C-5 Fuel Assembly Liftoff Completed Amendment 8 C-6 Review of Stress Report Open C-7 Use of Code Cases Completed 12/17/84 C-8 Reactor Vessel Studs and Completed 5/24/85 Rev. 1 Fastners C-9 Containment Depressurization NRC Review Analysis C-10 Reactor Pressure Vessel Shield NRC Review Annulus Analysis C-11 Drywell Head Region Pressure NRC Review Response Analysis C-12 Drywell-to-Wetwell Vacuum NRC Review Breaker Loads C-13 Short-Term Feedwater System Complete 4/22/85 Analysis C-14 Loss-of-Coolant-Accident Completed 3/1/85 & 6/12/85 Analysis C-15 Balance-of-Plant Testability Completed Amendment 8 Analysis C-16 Instrumentation Setpoints Partial Response 2/15/85 C-17 Isolation Devices Open M P85 27/10 2-mr
3 R.
L.
Mittl to A.
Schwencer 4
Item No.
Subject Status ltr. dated C-18 Regulatory Guide 1.75 NRC Review C-19 Reactor Mode Switch NRC Review C-20 Engineered Safety Features Open Reset Controls C-21 High Pressure Coolant Injection Completed 7/1/85 Initiation C-22 IE Bulletin 79-27 Completed Amendment 8 C-23 Bypassed and Inoperable Status NRC Review Indication C-24 Logic for Low Pressure Coolant Open Injection Interlock Circuitry C-25 End-of-Cycle Recirculation Pump Completed 3/1/85 Trip C-26 Multiple Control System Failures NRC Review C-27 Relief Function of Safety / Relief Completed 2/15/85 Valves C-28 Main Steam Tunnel Flooding Completed 5/24/85 Analysis l
C-29 Cable Tray Separation Testing Completed 4/4/85 C-30 Use of Inverter as Isolation Completed 3/7/85 L
Device C-31 Core Damage Estimate Procedure Completed 6/24/85 C-32 Continuous Airborne Particulate Completed 7/1/85 Monitors C-33 Qualifications of Senior Radiation Open Protection Engineer i
C-34 Onsite Instrument Information Completed 7/1/85 C-35 Airborne Iodine Concentration Completed 6/18/85 Instruments M P85 27/10 3-mr
4 R.
L. Mittl to A.
Schwencer Item No.
Subject Status ltr. dated C-36 Emergency Plan Items Partial Response 11/9/84, 1/16/85, 2/7/85 &
4/4/85 C-37 TMI Item II.K.3.18 Partial Response 3/1/85 &
4/22/85 e
MP 85 27/10 3-mr
ATTACHMENT 2 ITEM NO.
SER SECTION SUBJECT C-21 7.3.2.9 High pressure coolant injection initiation C-32 12.3.4.2 continuous airborne particulate monitors C-34 12.5.2 Onsite instrument information DJD:mr M P85 27/10 5 -mr i
ATTACHMENT 3 l
1 M P85 27/10 6-mr
SER CONFIRMATORY ISSUE 21 (7.3.2.9)
HIGH PRESSURE COOLANT INJECTION INITIATION IEEE Std. 279 requires that the protective system automati-cally initiate the protective action of the appropriate safety system when a plant condition reaches a predetermined level.
Manual initiation capability is also required.
Once initiated, either automatically or manually, the initiation must cause an action, or a sequence of actions, that results in providing the necessary safety function.
The "go to com-pletion" criterion is satisfied typically with initiation seal-in circuitry.
The applicant has proposed replacing the K32 contact in the pump discharge valve (E41-F006) logic circuit with contacts from a relay that is sealed-in upon HPCI initiation (whether automatic or manual).
This is acceptable to the staff, and it concludes that this modified design will meet the requirements of IEEE Std. 279.
The staff will confirm that the HPCI design meets the requirements of IEEE Std. 279 when the final drawings are submitted to the staf f.
Response
Attached is one copy of the following drawings showing the modification to the HPCI initiation contact for valve E41-F006:
ELEM DIAG-HPCI System - Dwg. No. 108 55-N1-E41-10 4 0-62 ( 3 )-14 ELEM DIAG-HPCI System - Dwg. No. 10855-N1-E41-1010-62(5)-13 ELEM DIAG-HPCI System - Dwg. No. 10855-N1-E41-1040-62(ll)-14 r
M P85 119/15 3-cag
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I APERTURE CARDS
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( ADDITIONAL DOCUMENT PAGES FOLLOW )
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SER CONFIRMATORY ISSUE 32 (12.3.4.2)
CONTINUOUS AIRBORNE PARTICULATE MONITORS The applicant will provide the locations, quantity, and type of continuous airborne monitors to be used by July 1, 1985.
On the basis of the applicant's commitment to provide the above information at a later date, this is a confirmatory item.
Response
FSAR Section 12.3 and Table 12.5-1 have been revised to pro-vide the requested inf ormation.
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The ventilation systems are designed to prevent the spread of airborne radioactivity into normally occupied areas.
4 b.
Highly radioact_ive piping / components are not located in normally occupied areas.
l Certain activities, such as refueling, solid waste handling, or turbine teardown, may increase the possibility of -encountering i
significant airborne activities in some normally occupied areas.
Continuous local airborne monitoring, will be provided during these activities, as needed.
d u.ri ng normal c> personD Exposure of personnel to high concentrations of airborne activity in radiation areas will be prevented through in-plant surveys and portable particulate and iodine sampling monitors prior to personnel entrance.
Continuous monitoring will be provided as required by area conditions and the nature of the entry.
The locations of portable monitors, capable of detecting 10 MPC-hours of particulates and iodines, which will be positioned within the stationAto provide supplemental inplant monitoring of particulatesandiodinelevels,{WillbeprovidedbyJuly1, 1935.
The p0 itiening Of supplrcrnta_ centine :: mir :: niter: is per-t-Of the R distien Pretecti0n Pr0grs= :nd : July 1,
??"5 d:t i:-
eenststent--with-f4aalleing other details of the program--41,e.,
1-nstrument-and-equipment-eaMbrat4en).
The Ice:tica, quantity, 2nd ceniter type rili ha previd:d :t th:t ti;;.
Administrative i
control will prevent inadvertent entry of personnel into normally) unoccupied areas (Zone III and above).
The provisions discussed above ensure that personnel will not be inadvertently exposed to significant concentrations of airborne activity.
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12.
3.5 REFERENCES
12.3-1 J.J. Martin and P.H. Blichert-Toft, " Radioactive Atoms, Auger Electrons, and X-Ray Data," Nuclear Data Tables, Academic Press, October 1970.
12.3-2 J.J. Martin, Radioactive Atoms Supplement 1, ORNL 4923, Oak Ridge National Laboratory, August 1973.
12.3-3 W.W. Bowman and K.W. MacMurdo, " Radioactive Decays Ordered by Energy and Nuclide," Atomic Data and 12.3-44 Amendment 8 i
. SSR c - - _ - -
Insert #1 are identified in Figures 12.3-60 through 12.3-71.
During outages or special evolutions, these monitors may be augmented or shifted, as needed.
The quantity required during normal operations and monitor type are identified in Table 12.5-1.
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TABLE 12.5-1 TYPES OF PORTABLE IMTRUttENTS 1
Radiation Calibration Approximate Freemency In*- ' ' use Inventory.
Zygg Instrument (88 ggggjad.
tamisation RO-2 beta-gamma 0-5000 m/hr 6 months Dose Rate Surveys 10 i
RO-2A beta-gamma 0-50 R/hr 6 months Dose Rate Surveys 10
-Pf9=64
-gamma N mentius
-some-Rate-eeuweys
--.4-.
SRPD's gamma various 6 mos/3 mos(a) Personnel Monitoring (exposure) 1700 i
RO-7 gamma 0-19.99 ER/br 6 months Accident surveys (R.G. 1.97) 2
?'
Proportional j
PIEt-4 neutron 0-5000 aren/hr 6 months Dose Rate Surveys 3
scalers alpha, beta,qamma 0-10* counts 6 months Air Samp & Swipe Counting 2
i G-M Teletector beta-gassa 0-1000 R/hr 6 months High Range Dose Rate Surveys 16 RM-14 beta-gamma 0-50,000 c/m 6 months Personnel Monitoring (contamination) 20
-S-64045
-gemme-6-96-R/he M
- 52t:
?-- - ;-;;.
i;;; -----
" 00 a.";..--
4-monther h
a,-- L i; Cz_,;
-94*
MS-3 beta-gamma 0- soo,eoo 8'/m 6 months Continuous Air Monitoring
-le IS Scalers beta-gamma 0-10* counts 6 monthe Air & Swipe Counting g
E-5JO be.ta.3amma
..ao ent/hr-4,rnentns no w hos e Aa.fe. S u >V e y 3 go Scintillation r Aro.63 g
fac=te
- alpha 0-700,000 c/m 6 months Alpha Surveys 4
scalers alpha, beta, gamma 0-10* counts 6 months Air & Swipe Counting 2
(8 3 or equivalent instrument (88 Self-reading pocket dosisators used for permanent exposure records shall be calibrated every 3 months.
.j 4
4 i
i 4
l Amendment 1
SER CONFIRMATORY ISSUE 34 (12.5.2)
ON-SITE INSTRUMENT INFORMATION Radiation and contamination survey instrumentation at Hope Creek includes various alpha, be ta, gamma, and neutron sur-vey meters and instruments for obtaining samples of surface and airborne contamination.
RG 1.97 states that portable instrumentation should be available to analyze and assess post-accident conditions.
The range should be 10-3 rem /hr to 10+4 rem /hr for photons arid 10-3 rad /hr to 10+4 rad /hr for beta radiation and low-energy photons.
Hope Creek has two portable ion-chamber dose rate instruments capable of detecting radiation in these ranges.
The applicant will provide more details of the on-site instrument calibration capabilities, including sources, equipment, and methods, by July 1, 1985.
This item is confirmatory pending receipt and review of this information.
Response
FSAR Section 12.5.2.2 has been revised to provide the requested information.
M P85 119/15 1-cag
'g The health physics work room complex is made up of areas for certain radiation protection functions permiting coordination of activities between the Salem and Hope Creek units.
These functions include personnel radiation dosimetry, issuance and processing, whole body counting, calibration and instrument repair, and respirator fit testing.
The radioactive source room located inside the guardhouse complex has storage and work facilities providing protection for surrounding areas during the use and manipulation of radiation sources for instrument and dosimetry calibrations and other related work.
Figures 12.5-4 and 12.5-5 show the health physics work room complex and the access-security control station, respectively.
12.5.2.2 Instruments and Equipment Instrumentation for detecting and measuring radiation consists of counting room equipment, portable instrumentation, and air samplers.
Capabilities for detecting alpha, beta, gamma, and neutron radiation are provided.
Sufficient inventory is provided to accommodate use, repairs, and calibration.
Det:il: ef the-Oncit in teunent calibratier capabilities, including sources e equipment, :nd ::th d: cre not presently included, since the-calibration facility i: in the early-planning-stage.--Onsi-te calibration ::p:bility detail: eill be e'esil:ble by July 1
- 1985, A: the pl:nning progre::::,-mere details will be included in the A dd lo.s ert 1.
l t
I I
I 12.5-6b Amendment 8
.Sc~x c -3 Y
Insert #1 Instrument calibrations include electronic and radiation calibration of dose rate and count rate instruments, counting scalers, and portal monitors.
It also include the flow calibration of portable air samplers, such a s AMS-3 's, Hi-Vols, H-809 Lo-Vols, RAP and RAS pumps utilizing aneomometers, flow meters and D/P gauges.
Electronic calibrations are performed utilizing various types of measuring and test equipment, such as current pulsers, digital volt meters, oscilloscopes, decade boxes and capacitance testers.
Radiation calibrations are performed utilizing several licensed and exempt radiation sources, depending on the type radiation the instrument detects.
For gamma survey instru-ments, Cs-137, with an energy of 662 kev, is the isotope chosen because it is comparable to the average gamma energy of the isotopes present in a typical primary reactor coolant sample.
Three Cs-137 sources are used for calibrations.
The irradiators used are the 100 mci Shepherd Model 28-5 and a 400 Ci Shepherd Model 89 box type, which is primarily used for instruments and a 3 Ci Shepherd Model 81-8A tower, which is used to irradiate thermoluminescent dosimeters (TLD's) and self-reading dosimeters (SRD's).
All irradiation sources are shielded consistant with the station ALARA program.
These sources are controlled and secured under the appropriate administrative, radiation protection and physical security procedures.
Beta measuring survey instruments are calibrated and their efficiencies for beta detection determined with a depleted Uranium slab.
This mylar-covered slab has a standard dose rate and is commonly used for this application.
Beta counting equipment is radiation calibrated using electroplated Tc-99 planchet-sized sources.
Alpha counting scalers and alpha survey instruments are calibrated with electroplated sources, as well.
These are either planchet-sized or provided in detector-sized jigs.
Neutron measuring instruments are calibrated with an encapsulated MRC 5.7 Ci AmBe source which is set-up for irradiation on the source range in a borated polyethelene
' block jig.
1 of 2
Various low-activity exempt check-sources (" button-type")
are also used to verify instrument response.
All instruments are calibrated in compliance with the American National Standards Institute (ANSI) N323 - 1978, which establishes calibration methods for portable radiation protection instruments used for the detection and measure-ment of ionizing radiation and radioactive surface contamination.
l l
1 i
4 JS:bp IK 27 2/3 2 of 2
- tien.
All Of the plenting will-ineerper:t Otraderd he:lth phy ie: pr::tice: : d the reex : detiens-of--th:
- preprirte
- 21
- t105: : d pu51icattons, I
l Sufficient chemical supplies, chemistry laboratory equipment, and l
analytical instruments are available to perform the required i
sample preparations and analyses in support of radiation l
protection functions.
l 12.5.2.2.1 Chemistry Laboratories The chemistry facility consists of two laboratories: one that handles low level or background level samples and a second that handles medium and high radiation samples.
I The laboratories are equipped with constant air flow fume hoods.
The fume hoods permit preparation and processing of contaminated s
l samples under controlled conditions.
12.5.2.2.2 Counting Rooms l
Plant system samples processed in the chemical laboratories for I
activity analysis and isotopic identification are transported to the chemistry counting room.
Samples direct from the plant, such as air samples and smears, are transported to the radiation protection counting room.
Equipment is available in both counting rooms for gross alpha, gross beta, and gross gamma activity measurements and for determination of the activity levels of specific isotopes.
Both counting rooms are temperature-controlled and the voltage supply is regulated for instrument stability.
Major instrumentation in both counting rooms includes a computer i
programmed multi-channel analyzer using germanium detectors, or other detectors appropriate for specific isotopic identification; gas flow proportional counters, with and/or without windows, for i
filter samples, smears, and planchetted water samples; and a l
gross beta-gamma counter.
The chemistry counting room also contains a liquid scintillation counter for beta emitters such as j
l 12.5-7 Amendment 8 SeGt e-34 l ~
..