HBL-87-066, Forwards Rev 3 to Proposed Tech Specs for Safstor.Revs Reflect Util 870821 Response to NRC Request for Addl Info
| ML20236R368 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 11/16/1987 |
| From: | Shiffer J PACIFIC GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| HBL-87-066, HBL-87-66, NUDOCS 8711230242 | |
| Download: ML20236R368 (53) | |
Text
{{#Wiki_filter:_ - _ _ _ . __ l PACIFIC GAS AND E LE C T RI C C O M PANY b6W[3 l 77 BEALE STREET
- SAN FRANCISCO, C ALIFORNI A 94106 . (415) 781 4211 . TWX 910-372-6587
_,a,,,,, November 16, 1987 VFCE PRE 510ENT
.=ua= =ia =~i=^= PG&E Letter No.: HBL-87-066 Nuclear Regulatory Commission !
Attn: Document Control Desk 1 Washington, D.C. 20555 i Re: Docket No. 50-133, OL-DPR-7 Humboldt Bay Power Plant, Unit 3 i SAFSTOR Technical Specifications, Revision 3 ) Gentlemen: PG&E letter dated March 20, 1987, (HBL-87-015) transmitted Revision 2 to the ! proposed SAFSTOR Technical Specifications for Humboldt Bay Power Plant, ! Unit 3. This letter provides Revision 3 to PG&E's proposed Technical Specifications for SAFSTOR. Each proposed modification is indicated by a revision bar with an R3 (Revision 3) on the right margin of the page. These J' revisions have been made to reflect PG&E's responses provided in a letter dated August 21, 1987 (HBL-87-052) to the NRC's request for additional 4 information on the proposed SAFSTOR Technical Specifications. Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope. Respectfully submitted, 4 P eifi as and lectri Company 0711230242 871116 PDR ADOCK 05000133 1 PDR P By - 4 P s n! l Howard V. Golub Nuclear Power Generation i Richard F. Locke i Attorneys for Pacific Subscribed and sworn to before me Gas and Electric Ccepany this 16th day of November 1987 By / d
' Richard F. Locke 8 Q Niincy J. L'em(shary Public in SEAL and for the City and County of San Francisco, State of California Enclosure My commission expires April 27, 1990.
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- OFFICIAL SEAL NANCY L LEMASTER l cc: w/ enc: P. B. Erickson (2) lh[g.
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- O* OI U My Commission Expires April 27 1990 Service List (Decommissioning) Lunnunuumuumumnumannanmum, mismn i IL
DOCKET NO. 50-133 APPENDIX A TO POSSESSION-ONLY LICENSE NO. DPR-7 TECHNICAL SPECIFICATIONS FOR DECOMMISSIONING OF HUMBOLDT BAY PGHER PLANT UNIT NO. 3 PACIFIC GAS AND ELECTRIC COMPANY DATE: 1742S/00 K 3 Revisiong
l l CONTENTS l I. INTRODUCTION I-1 A. Scope I-1 B. Definitions I-1
- 1. Administrative Controls I-l
- 2. Design Features I-2
- 3. Elevation I-2
- 4. Offsite Dose Calculation Manual I-2
- 5. Operable-Operability I-2
, 6. Operating Limits I-2 l 7. Operating Requirements I-2
- 8. SAFSTOR I-2'
- 9. Spent Fuel I-2 !
i II. SITE II-l A. Location 11-1 33-B.
'fjad m clu;4cn Areas 11-1 .j i
C. Principal Activities II-l III. STRUCTURES III-l ) 1 A. Design Features III-l
- 1. Refueling Building III-l
- 2. Spent fuel Storage Pool III-1 B. Operating Limits and Requirements III-l
- 1. Refueling Building III-l
- 2. Spent Fuel Storage Pool III-2
- 3. Neutron Absorber Surveillance Program III-2 IV, SERVICE SYSTEMS IV-1 A. Design Features IV-1
- 1. Refueling Building Ventilation System IV-1
- 2. Spent Fuel Storage Pool Service System IV-1
- 3. Fire Protection System IV-1 i
- 4. Electrical Systems IV-2 B. Operating Limits and Requirements IV-2 l
- 1. Refueling Building Ventilation System IV-2 i
- 2. Spent Fuel Storage Pool Service System IV-2 !
- 3. Fire Protection System IV-2 ,
- 4. Fire Hose Stations IV-4 i
- 5. Penetration Fire Barriers IV-5 '
- 6. Electrical Systems IV-5 3 \
1742S/00 K Revision / _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ A
I I CONTENTS
)
EAgf V. MONITORING SYSTEMS V-1 1 A. Design features V-1
- 1. Stack Gas Monitoring System V-1
- 2. Process Hater Monitor V-1
- 3. Area Monitors and Portable Monitoring Equipment V-1
- 4. Offsite Environmental Monitoring Station . V-2 3
- 5. Spent Fuel Storage Pool Water Level Monitors V-2 j
- 6. Onsite Environmental Monitoring Stations V-2 j B. Operating Limits and Requirements V-2 l 1. Stack Gas Monitoring System V-2 'l
- 2. Process Hater Monitor V-2 '
- 3. Area Monitors and Portable Monitoring Equipment V-3 !
- 4. Offsite Environmental Monitoring Station V-3 j
- 5. Spent Fuel Storage Pool Hater Level Monitors V-4. j g Og5, En rongngMnitoringStations V-g3 VI. HASTE DISPOSAL SYSTEMS VI-1 A. Design Features VI-1
- 1. Liquid Radioactive Haste System VI-1
- 2. Solid Radioactive Haste System VI-2
]
B. Operating Limits and Requirements VI-2 l
- 1. Liquid Radioactive Haste System VI-2
- 2. Solid Radioactive Haste System VI-2
- 3. Gaseous Effluents VI-3 !
VII. ADMINISTRATIVE CONTROLS VII-1 A. Responsibility VII-1 , B. Offsite Organization VII-1 C. Plant Organization VII-1
- 1. Requirements for the Shift Operating Organization VII-1
- 2. Plant Staff Qualifications VII-4 l
- 3. Fire Protection Program VII-6 '
- 4. Training VII-6 D. Review and Audit VII-7 i
- 1. Plant Staff Review Committee VII-7
- 2. General Office Nuclear Power Plant Review and Audit Committee VII-9
.S ' l l 1742S/00 K Revision y.
i
CONTENTS EAER E. Procedures VII-12
- 1. Detailed Procedures VII-12
- 2. Procedure Review VII-13
- 3. Procedure Changes VII-13
- 4. Emergencies Not Covered by a Procedure VII-13 F. Site Emergency Plan VII-13 G. Operational Testing VII-13 H. Reporting Requirements VII-13
- 1. Annual Report VII-13
- 2. Non-Routine Reports VII-14
- 3. Semiannual Effluent Release Report VII-14
- 4. Special Reports VII-14 I. Record Retention VII-14
- 1. Records'and Logs VII-14
- 2. SAFSTOR Duration VII-15 l J. Radiation Protection Program VII-16 K. High Radiation Area VII-16 iii 1742S/00 K Revision 1
l 1 i l I LIST OF TABLES NA Title EAge III-l Refueling Building Personnel, Equipment Entry, and III-3 Ventilation System Penetrations III-2 Spent Fuel Storage Pool Water Chemistry and III-4 Activity During SAFSTOR IV-1 Fire Hose Stations IV-6 LIST OF FIGURES Title EAgt lW3 HL. litosERT I l
-1 Offsite Organization Chart VII-2 VII-2 Plant Staff Organization Chart VII-3 frriscRT L .
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- 7 3
1742S iv RevisionJ/ ,
I. INTRODUCTION A. SCOPE These Technical Specifications set forth the principal design features and operating limits and requirements for Unit No. 3 (the Unit) at Pacific Gas and Electric Company's (the Company) Humboldt Bay Power Plant (the Plant). The Unit originally operated as a nuclear power plant utilizing a single-cycle, natural circulation, boiling water reactor and associated turbine generator. As part of the decommissioning of the Unit, most systems have been secured. Systems remaining in operation are utilized for the storage of spent reactor fuel, monitoring and surveillance of the Unit during the SAFSTOR continuing care period, and for the processing of radioactive wastes generated during the SAFSTOR period. Systems and components which have been secured are not described in these Technical Specifications. Section II of these Technical Specifications describes the site. Sections III through VI describe structures, systems, and components utilized during the SAFSTOR period and specify the conditions under which they shall be controlled and monitored. Each of the Sections III through VI consists of:
- 1. A description of the design features which are considered to be significant. Where thermal, hydraulic, and nuclear characteristics of various systems are given, + R3 manufacturingtolerancesunle[herearesubjecttonormal s cific tolerances are stated.
- 2. A list of the coeratina limits and r uirements. Whenever a condition occurs which requires corrective action to ensure operation or maintenance within these limits and requirements, such action shall be taken in a timely manner. i Section VII of these Technical Specifications covers administrative and I procedural requirements, including the review of proposed changes in design and operating lirits, requirements and procedures, and presents procedures for normal and emergency conditions during the SAFSTOR period.
B. DEFINITIONS
- 1. ADMINISTRATIVE CONTROLS: The provisions relating to the organization and management, procedures and record keeping, review and audit, and reporting which are necessary to ensure maintenance of the Plant in a safe condition during SAFSTOR.
1-1 3 1742S/00 K Revi sion ,V '
2.- DESIGN FEATURES: .Those features of the Plant which, if altered or. modified, could have a significant effect on the ability of the system, component or structure to perform its intended function.
- 3. ELEVATION: All elevations shall apply.to a datum of mean lower low water (MLLH) level g ,Q f,foy J
- 4. OFFSITE DOSE N CULATION MAN TheL:offsite dose calculation manual (00CHhshall contain the methodology and parameters used in 'R3 the calculation of offsite doses and concentrations due to radioactive gaseous and liquid effluents and in the.' calculation of gaseous and liquid effluent monitoring alarm setpoints.
- 5. OPERABLE - OPERABILITY: A system, subsystem train, component, or device may be considered OPERABLE or have OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation ' controls, normal and emergency electric power .
sources, cooling or seal _ water, lubrication subsystem, train, J component, or device required to perform its function (s) are also capable of performing their related support function (s).
- 6. OPERATING LIMITS: The lowest functional capability, performance )
levels, or safety limits of structures, systems, or components ! required during SAFSTOR.
]
- 7. OPERATING REQUIREMENTS: Those requirements relating to operation, test, calibration, surveillance, or inspection to ensure that operating limits will be met. .,
- 8. SAFSTOR: The mode of decommissioning which consists of placing _the I Unit into a state of protective storage.- Spent fuel will remain in the Spent Fuel Storage Pool until shipped offsite for disposal.
Systems necessary to support the storage of the spent fuel, for monitoring and surveillance of the Unit, and for storage and processing of radioactive wastes will remain operational..
- 9. SPENT FUEL: Nuclear fuel which has been removed from the Reactor -j Vessel after.having been used in critical, power generation.- l 1
I i 1 f i I-2 17425/00 K Revision
l II. SlIE ! I A. LOCATION l The Unit is located in Humboldt County, California, approximately 4 miles I southwest of the center of the city of Eureka, on a site owned and I controlled by the Company. l TLfNT \ B. --E XC LUCION AREAS The 46c 4,h cakJia6gs, UWkNh?'jnnsfcftd
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tre contrc!!ed by the Company. C. PRINCIPAL ACTIVITIES The principal activities of the Plant are those related to the generation and transmission of electric power and the associated service activities. Activities associated with the Unit consist of storage and surveillance of spent reactor fuel, monitoring and surveillance of the decommissioned facility, and operations and maintenance to support the D 6 ctivities g ine Unit is located Edjscent te two eil end/or neturei g ,fycled, 50,00 kilewett steam turbine-iienerster Units ' Unit Nos. I p3 4 m accuAnce n.ni4 holcfovq Guik I.04, suten c.f. l l 11-1 3 1742S/00 K Revi sion,P
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i III. STRUCTURES The Refueling Building and the Spent Fuel Storage Pool will contain the spent fuel during the SAFSTOR period. This section describes the design features and operating limits and requirements which will continue through the SAFSTOR period. A. DESIGN FEATURES
- 1. Refuelina Building - The Refueling Building is a reinforced concrete structure located immediately above the Reactor Caisson. The Spent Fuel Storage Pool is located within the Refueling Building.
l The building functions as a weather enclosure, contamination control barrier, and radiation shield. Personnel and equipment entry and ventilation system penetrations in the Refueling Building are given in Table III-1.
- 2. Soent Fuel Storage Pool - The Spent Fuel Storage Pool is a reinforced concrete structure integral with the Reactor Caisson. It extends to a depth of 26 feet except for a cask loading pit in one corner which extends to a depth of 36 feet. The water in the pool provides shielding and contamination control. A stainless steel liner shall completely cover the inside surfaces of the Spent Fuel Storage Pool with a nominal gap of 1/4 inch between walls / floor and liner.
In the event of a failure of the spent fuel racks, criticality is prevented by storing the fuel assemblies in containers constructed of neutron absorbing material. All spent fuel assemblies except assembly UD-6N shall be stored in the containers. The containers shall be attached to the fuel assemblies. A Spent fuel Storage Pool cover shall normally be installed over the Spent Fuel Pool. The cover shall incorporate the following characteristics: o A structure designed to preclude droppage of objects into the poel o A contamination control barrier B. OPERATING LIMITS AND REQUIREMENTS
- l. Refuelina Buildino - A thorough visual inspection of the Refueling Building shall be conducted at least quarterly. Evidence of deterioration shall be evaluated with regard to the function of the building as a weather enclosure, contamination control barrier, and radiation shield.
l III-l 1742S/00 K Revision 2
1 l l
- 2. Soent Fuel Storaae Pool
~
l.r/vsERT 11
- a. fHaterLevel-HaterlevelintheSpentFuelStoragePoolshall jbemaintainedatanelevationgreaterthan10.5 feet. The 'R3 x water level between the liner and the concrete walls shall be {
quaintained below elevation +9 inches. j l.mds 1
- b. Spent Fuel Pool Hater Ouality - Hater quali y in the Spent Fuel '
Storage Pool shall be maintained within the specified in Table III-2. Spent Fuel Storage Poo' er shall be sampled and analyzed at least once per q= rt ?. f water quality limitsareexceeded,actionshallbe9akentorestorethewater Uf, quality to within limits and an evaltation h411 be conpuctgd to determine he c the hwu+s specsged xe 6&ause.ge nut De r,cty g my
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- 3. Neutron Absorber Surveillance Proaram 4 ,,po;lcp 3o aqs,
- a. Samples of the neutron absorbing material used to fabricate the spent fuel assembly containers shall be suspended in the spent fuel storage pool in the vicinity of the spent fuel assemblies. A program shall be established to remove representative samples at specified intervals for examination and analysis to verify that the Boron-10 loading is greater than 0.005 grams per square centimeter.
l l 4 l l III-2 .5 1742S/00 K Revision y _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - - _ _ - - _ _ _ - - - - - - _ - - - - - - - - - - - - - - - - - - - - - 1
1 1 l TN$ j / - f Hater Level - Pool water level shall be maintained at an elevation greater than 10.5 feet (within 1.5 feet below the main floor of the refueling building. The water level between 4 the liner and the concrete walls shall be maintained below I elevation +9 inches (11.25 ft or greater below the main floor of the refueling building). The main floor of the refueling building is at the +12 feet elevation. i l 1 I I i l 1 I j I 3121H
1 l Table III-l REFUELING BUILDING PERSONNEL, EQUIPMENT ENTRY, AND VENTILATION SYSTEM PENETRATIONS I Penetration No. Size Type of Closure Railroad door entry 1 15 ft x 16 ft Normally locked entry Personnel air lock 2 25-1/2 in. x Two mechanically interlocked 66 in. doors in series Caisson personnel 1 3 ft dia Hatch and doors in series (a) emergency exit shaft Main ventilation 1 16 in. dia One 16 in air operated system supply duct isolation valve Main ventilation 2 16 in. dia Two 16 in, air operated system exhaust ducts isolation valvestb> l Dry well purge 1 14 in. dia Two 8 in. air operated system exhaust duct isolation valves I (a) Hatch locked and cannot be opened from outside the exit shaft except with l key. The lock will not prevent emergency exit from the caisson. (b) Two 16-inch exhaust ducts from the refueling building join together to form a single duct. The two isolation valves are in series in ihis duct. In addition to the ventilation system penetrations listed above, two ducts associated with the Gas Treatment System are considered building i penetrations. Valves in the ducts shall normally be closed, but shall be 1 opened when the refueling building ventilation exhaust is through the gas treatment system. l l l III-3 1742S/00 K Revision 1
l Table III-2 4 SPENT FUEL STORAGE POOL HATER CHEMISTRY AND ACTIVITY DURING SAFSTOR Lumik Parameter A c:pt!M e init D
- 1. pH 5.3 to 6.5 1
- 2. Chlorides (b) 0.5 ppm (maximum) l l
- 3. Conductivity 10.0 umho/cm (maximum)
- 4. Total Spent Fuel Pool dissolved 1.0 x 10-4 UCi/ml (maximum) activity (c) 1 (a) Verification shall be accomplished by analysis of samples taken at least once each quarter.
(b) Chloride analysis is only required if conductivity exceeds 2.0 umho/cm. (Reference NRC Regulatory Guide 1.56, Figure 2.) l (c) By proportional counter calibrated with Cs-137 l
.3 III-4 Revision [
1 IV. SERVICE SYSTEMS The Refueling Building Ventilation System, the Spent Fuel Pool Service System, the Fire Protection System, and several Electrical Systems provide services which maintain habitability and safe conditions within the Plant for the ! SAFSTOR period. This section describes the design features and operating l limits and requirements which are important to the continued operation of l these systems. ; i A. DESIGN FEATURES ; l
- 1. Refuelina Buildina Ventilation System - The Refueling Building I Ventilation System shall provide normal ventilation to the Refueling !
Building. The system shall exhaust to the main ventilation exhaust ! stack. Isolation valves shall be provided to permit isolation of the Refueling Building.
- 2. Soent Fuel Storace Pool Service System - Makeup water for the Spent i Fuel Storage Pool shall be provided from the demineralized water l system. The capacity of the demineralized water tank shall be 5,000 gallons. Water to the demineralized water tank shall normally be supplied from Units No. I and 2 condensate storage tanks.
Emergency makeup water to the Spent Fuel Storage Pool shall be available from the plant fire system. Spent Fuel Storage Pool water quality shall be maintained using either of two spent fuel pool circulating water pumps to circulate pool water through a demineralized. j Hater level in the gap between the spent fuel pool liner and the l concrete wall shall be maintained using a liner gap pump which ! discharges to the liquid radioactive waste collection system.
- 3. Fire Protection System - The fire protection system consists of the fire water svstem, fire hose stations, and penetration fire barriers:
PtNsEYT Ll
- a. 'The fire water system shall consist of three plant fire pumps each rated at 500 gpm at 120 psig discharge pressure. These pumps shall take suction from the 300,000 gallon Plant raw g3 water storage tank. Two of these pumps shall be powered from j separate 480 volt Unit No. I and Unit No. 2 AC systems. The f
, third pump shall be diesel-powered. The pumps shall start t automatically to maintain system pressure. a
- b. Fire hose stations in the Unit shall consist of those stations and equipment listed in Table IV-1.
- c. Penetration fire barriers shall be provided for penetrations between the Control Room and Feed Pump Room, between the Feed Pump Room and the Refueling Building, and between the Control Room and Refueling Building. Penetration fire barriers shall IV-1 3 1742S/00 K Revision P
/ tVSERT' 2L i The fire water system shall consist of three plant fire pumps, each rated for 500 gpm at a discharge pressure of 120 psig.
These pumps shall take suction from the 300,000-ga11on raw water storage tank. The raw water storage tank shall have a low level alarm set at 200,000 gallons. Two of these pumps shall be electrically powered: one from the Unit 1 480-volt system, and the other from the Unit 2 480-volt system. The third pump shall be diesel powered. The pumps shall start automatically to maintain system pressure. 1 l l l l i i 1 i i l I l 1 I 1
---_-_______.__________________g
l l be passive devices to ensure that a fire will be confined or adequately retarded from spreading to other portions of the j facility.
- 4. Electrical Systems - Switchgear shall be provided so that any one of three independent power sources may sL9 ply the Unit's electrical equipment. These power sources are: Lnit No. 1. Unit No. 2, and-the Plant 60 KV bus.
B. OPERATING LIMITS AND REQUIREMENTS
- 1. Refuelina Buildino Ventilation System
- a. The Refueling Building Ventilation System shall be operated to maintain a negative pressure of at least 1/4 inch of water whenever spent fuel movements are taking place or whenever work which may potentially damage spent fuel assemblies is in progress.
l
- b. The capability of the Refueling Building Ventilation System to maintain a negative pressure of 1/4 inch of water in the Refueling Building shall be tested at the following times:
(1) prior to removing the spent fuel pool cover; (2) after any opening of the railroad door; and (3) after maintenance which may have affected any of the Refueling Building penetration closure seals. If not required for these reasons, the test shall be performed at least once each quarter.
- 2. Soent Fuel Storace Pool Service Systems
- a. A minimum of 2,000 gallons shall be maintained in the demineralized water tank.
i b. At least once per 31 days, the operability of the Spent Fuel. I Storage Pool liner gap pump shall be verified by pumping the liner gap to the minimum of the operating range specified in i l Section III.B.2.a. ' i
- 3. Fire Protection System i
i l a. The fire protection system shall be OPERABLE with: (1) Two plant fire pumps each with a capacity of 500 gpm with I their discharge aligned to the fire suppression header. (2) A minimum of 200,000 gallons in the Raw Hater Storage. Tank. (3) An OPERABLE flow path capable of taking suction from the water supply tank and transferring the water through the distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the front valve in each hose standpipe listed in Table IV-1. i IV-2 1742S/00 K Revision 2
1
- b. If the Fire Water System is inoperable, the system e all be restored to OPERABLE status within 7 days or a Sper 9 ' Report Nhc h om) shall be prepared and submitted to the tirs ter of ..re-Regien V Ad e shfu Degu!atcry Oper:t!0n: 00) Of'ke within 30 days outlining the g3
-fot 'R98co tr p!!n: :nd procedure: to b: u::d to ar0 Vide for los; ef redundancy h thi: :y;M'h.leCompsituNmmunes -bleu ad a se of couach athon,
- c. Inspections and Tests:
fo d (1) At least once per 7 days, the 3water supply volume shall be 'R3 verified. (2) At least once per 31 days, on a STAGGERED TEST BASIS, each I operable pump shall be started and operated for at least 15 minutes on recirculation flow. 1 (3) At least once per 31 days, it shall be verified that each valve (manual, power-operated, or automatic) in the flow 4 path is in its correct position. l (4) At least once per 12 months, each testable valve in the i flow path shall be cycled through at least one complete 1 cycle of full travel. (5) At least once per 18 months: I o A system functional test shall be performed which includes simulated automatic actuation of the system throughout its operating sequence.
- l o Each pump shall be verified to develop at least 450 gpm flow at a total head of 240 feet.
o Each fire pump shall be verified to start I (sequentially) at a sustained fire suppression water (O M k loalcal abm R3 i l shabe $}once At temperprpsure 3 yFars, f nQegs,tg45gs,i .feaska%rh ic e 2 5 % (@7 be performed in accordance with Chapter 5 11,
. Section [R3
- Fire Protection Handbook," 14th Edition, published by National Fire Protection Association.
(y The fire pump diesel engine shall be demonstrated operable l R3 8 as follows: o At least once per 31 days:
- The fuel storage tank shall be verified to contain
, at least 150 gallons of fuel. 1 The diesel shall be verified to start from ambient conditions and operate for at least 20 minutes. l l IV-3 3 1742S/00 K Revision y
o At least once per 92' days, a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, shall be verified to be within the acceptable limits specified in Table 1 of ASTM D-975-74 with respect to viscosity, water content, and sediment. o At least once per 18 months: The diesel shall be subjected to manufacturer's recommended servicing prescribed for operating hour intervals of 500 hours and less. The diesel shall be verified to start from ambient conditions on the auto-start signal and operate for at least 20 minutes while loaded with the fira pump. (Jd The fire pump diesel starting 12-volt batteries and i 9 chargers shall be demonstrated OPERABLE by: 3.3 o At least once per 31 days: The electrolyte level of each battery shall be verified to be above the plates. Each battery's overall voltage shall be verified to be no less than 12 volts. o At least once per 92 days, specific gravity shall be verifiedapp cpriate for ccr,"r.ced service of the - 73 battery. fo Ioc /.l % org n d r-o At least once per 18 months: The batteries, cell plates, and battery racks shall be verified to show no visual indication of physical damage or abnormal deterioration. The battery-to-battery and terminal connections shall be verified to be clean, tight, free of corrosion, and coated with anticorrosion material. ! 4. Fire Hose Stations
- a. The fire hose stations listed on Table IV-1 shall be OPERABLE (
l whenever equipment in the area is required to be OPERABLE. l
- b. When a hose station required to be operable is inoperable, an additional equivalent capacity hose be routed to the unprotected area from an operable hose station within 1 hour,
- c. Inspections and Tests Each fire hose station shall be verified operable:
I IV-4 3 1742S/00 K Revision # 1
(1) At least once per 31 days, by visual inspection of the station, to ensure that all equipment is available. (2) At least once per 18 months, by removing the hose for inspection and re-racking and replacing all gaskets in the couplings that are degraded. (3) At least once per 3 years, by partially opening each hose station valve to verify valve operability and no blockage. (4) At least once per 3 years, by conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at that hose station.
- 5. Penetration Fire Barriers
- a. Penetration Fire Barriers shall be functional at all times.
- b. Hith a Penetration Fire Barrier inoperable, a continuous fire i detection capability shall be established on at least one side i of the affected penetration within 1 hour as long as equipment on either side of the barrier is required to be operable.
- c. Inspections and Tests - Penetration Fire Barriers shall be verified to be functional by a visual inspection: ,
l o At least once per 18 months l o Prior to declaring a Penetration Firt Barrier functional following repairs or maintenance
- 6. Electrical Systems l
- a. Emergency Section, 480 Volt AC System - The emergency section normally shall be supplied from one of the Unit's two 480V AC buses. Provision shall be made for transferring the emergency section to a 480V AC source from Unit No. 1 or No. 2 and subsequently to an emergency generator rated at 60 kW. These transfers shall be initiated automatically by undervoltage relays on the emergency section. The emergency section shall supply the following loads:
(1) Emergency lighting (2) Hain annunciator system (3) The following radiation monitoring systems: stack gas; process monitor; and the Refueling Building monitors
- b. The transfer of the emergency 480 volt AC shall be tested for proper operation at least quarterly. This transfer shall be functionally tested annually with all loads connected so as to simulate emergency operation.
IV-5 1742S/00 K Revision 1
1 Table IV-1 1 FIRE HOSE STATIONS 1 Fire Hose Station Location Size Type I l West wall reactor feed pump room 1-1/2" X 50' Hose reel spray nozzle opposite M-G sets , j Reactor feed pump room at foot 1-1/2" X 50' Hose reel spray nozzle j of stairs i i Refueling building north wall 1-1/2" X 50' Hose reel spray nozzle near air lock j i Refueling. building top of stairs 1-1/2" X 50' Hose reel spray nozzle I air lock North wall of Makeup Demineralized 1-1/2" X 50' Hose reel spray nozzle room East wall control room 1-1/2" X 100' Hose reel fog nozzle North wall of turbine wash down 1-1/2" X 100' Hose reel fog nozzle Roof of refueling building 1-1/2" X 100' Hose reel fog nozzle 4 IV-6 1742S/00 K Revision 1 l
V. MONITORING SYSTEMS A. DESIGN FEATURES
- 1. Stack Gas Monitorina System - A system shall be provided to determine routine releases of particulate radioactivity and to provide monitoring and annunciation of non-routine releases of radioactive noble gases. The stack gas monitoring system shall consist of a particulate filter holder, a beta sensitive detector system, and a sample pump to produce a sample flow controlled at approximately 2 cfm. The particulate filters are removed for laboratory counting. The detector system shall have two detectors (one is an operating spare) to respond to radioactive (beta emitting) gasses which pass through the system. The detector system shall be designed to be sensitive to Kr85 in the stack gas from approximately 5 x 10-7 to approximately 2 x 10-Z micro-curies /cc.
l
- 2. Process Water Monitor - A process water radiation monitoring system i
employing a gamma sensitive scintillation detector shall be provided to indicate, record, and annunciate high radiation levels in the radwaste discharge line to the circulating water system. The range of the monitor shall be from 10 to 106 cpm with a typical Cl sensitivity of 200 cpm per pC1/ml for Cs-137 and 450 cpm per pft/ml 7f.5 for Co-60. l
- 3. Area Monitors and Portable Monitorina Eauioment - Fixed gamma monitors with ranges of 0.01 to 100 mr/hr or 0.01 mr/hr to 10 R/hr l
! shall be installed at various locations throughout the Unit. The ! l outputs of these monitors shall be recorded in the control room. l l Each channel shall have an adjustable high radiation alarm which is I I annunciated. One area monitor shall be located in each of the following locations: o Refueling building, south wall access door o Refueling building, northwest access door l A high radiation signal from either of these channels shall provide l a Building Above Normal Radiation" signal which is annunciated in i the control room. These two area monitoring channels shall also provide gamma monitoring of the fuel storage areas. A high l radiation level signal from either of these channels shall sound the evacuation horns in the Refueling Building. In addition to the area monitoring system, suitable portable and fixed, alpha and beta-gamma detection instruments and beta-gamma dose rate instruments shall be provided for use of personnel entering the Unit radiation areas and radioactive materials areas and for analyzing samples and/or swipes. I V-1 17425/00 K Revision
i
- 4. Offsite Environmental Monitorina Stations - Four offsite environmental monitoring stations shall be maintained through the 1 SAFSTOR period. These represent a series downwind from the plant in i prevailing wind direction ranging from 0.25 mile to 11 6 miles from i Unit 3 These stations shall be equipped with dosimetry devices i which n be compared with hose used on-site, g i
( See 5tfe Z~l . i
- 5. Scent Fuel Storaae Pool Water Level Monitors - Two water level indicating devices shall be installed in the Spent Fuel Storage 1 Pool. The outputs of these monitors shall be indicated in the Control Room. Annunciation (visual and audible) of low water level j shall be provided in the Control Room. One of these monitors shall ,
CnAPD. ' DJ & l zhs ETT1.J l
- 6. Onsite Environmental Monitorina Stations - On-site monitoring 1 l stations include a continuous sampler within the discharge canal. R3 I dosimeters near the site perimeter fenceline. and monitoring wells. l B. OPERATING LIMITS AND REQUIREMENTS l
- 1. Stack Gas Monitorino System - The stack gas monitoring system shall be operable and capable of initiating the stack gas high radiation j level alarm whenever the ventilation system is in operation. It may '
be taken out of service for calibration or maintenance, but shall be returned to service as soon as practicable. The monitors shall be set to alarm at or below the level where the noble gas release rate would result in an instantaneous offsite concentration of airborne radioactive material equal to the appropriate value given in , 10 CFR 20, Appendix B. Table II, column 1. This alarm setpoint i shall be calculated in accordance with the ODCH. ' The calibration of these monitors shall be checked at least once i each year. Alarm functions shall be checked weekly for operability. i
)
The stack particulate filter will normally be removed for laboratory counting on a weekly schedule (sample intervals not to exceed 200 hours). i The vent header which collects all vents from the 11guld radwaste treatment facility shall be connected to the plant ventilation , exhaust system to permit monitoring by the stack gas monitoring l system. ,
- 2. Process Water Monitor - The monitor shall normally be operable to detect inadvertent discharge of radwaste. It may be taken out of service for calibration and maintenance but shall be returned to service as soon as practicable. When the monitor is out of service, any release shall be verified by analysis of duplicate independent ,
samples and independent verification of the valve lineup prior to the activity being released. : 3 V-2 Revision;V
stTr 3 l Onsite Environmental Monitorina Stations - Onsite monitoring stations shall include a continuous sampler for water in the discharge canal, dosimeters at or within the site perimeter fence line, and groundwater monitoring wells. The locations of the dosimeters and the wells are shown by Figures V-2 and V-3, respectively. The onsite groundwater monitoring program shall consist of five wells constructed in the vicinity of Unit 3. Two wells.(MH-1 and MH-11) shall serve as background (upgradient) monitoring wells. Three wells (MH-2, MH-4, and MH-6) are located downgradient of Unit 3 and shall serve as groundwater contamination detection wells. i 1 l I 1 i 3121M 1
The monitor shall be source-checked quarterly to assure proper dsc6pto,hpc I calibration. The monitor shall be set to alarm at or below 4he a C5 -137 c4 s x 4;;;i rh:re th: concentration ' "'~+4=i+" ia " '"* - " ' "-- " m M e muofme/ml g 5:t;; ,g eg33; g;;;jt: j; - g:1 te the 3777 77j:t: y;3 : ;5y:n ja M UD ?O ^.;; ndh 9. Td!: :, ;el=n L This elers,setpeint
^^"" 73
- h:!! be c;?: !:ted in ecdc e
,Mn.laa iin J.fv'~'d:. Alar nd 6kanodreoA shall be checked week 1 .. room cr ctions$ed
,0 I of V10- 6 mboCxesjm he coose unH be m " ve
- k wt3 9
- 3. Area Monitors and Port ble Monitorina Eauinment-d yh"N
- a. The area monitors shall normally be in service at all times.
They may be taken out of service for maintenance purposes but shall be returned to service as soon as practicable.
- b. The two monitors in the Refueling Building shall alarm at 15 mr/hr. At least one of these channels shall be available to monitor the fuel storage area and sound the evacuation horns in the Refueling Building. If this condition cannot be met, monitoring shall be accomplished with portable instruments whenever personnel are in the Refueling Building.
- c. The remainder of the area monitors shall be set to alarm either at 1 mr/hr or at a radiation level within a factor of two of ;
the normal maximum indicated radiation level.. ,
- d. The calibration of area monitors shall be checked at least once each quarter, a e ource-checked at least onceeachmonth[ndthe,moni,torsshall and sha# Le cc4 w ArnocBp p
- e. Portable radiation detection instruments shall be calibrated 4Tr 4c;;rd:::: eith ;;tabli;h;d ::hedule:. af lead annodp
- f. Fixed and portable equipment will be used to support the ,
following survey and sampling program: A gross beta-gamma . l radiation survey and a contamination survey of the Plant shall
~
be conducted at least quarterly to verify that no radioactive ' material is escaping or being transported through containment barriers. Contamination samples shall be taken along the most i probable path by which radioactive material (such as that , stored in the inner containment regions) could be transported j to the outer regions of the Plant and ultimately to the ! environs. , s
- 4. Offsite Environmental Monitorina Station.- If stray radiation R3 J chambers are used, they shall be monitor'ed every 14 to 15 days with average and maximum values reported annually. .If film packs are used, they shall be monitored monthly with average and maximum ,
values reported annually. If thermal luminescent detectors (TLDs) : are used, they shall be monitored at least quarterly with average and maximum values reported annually. I 1 l
.3 ,
V-3 Revisionf 1742S :
If the results from any station indicate that the total radiation dose would be 25 mr/ year or more above background, an investigation will be conducted and necessary mitigative actions taken.
- 5. Soent Fuel Storage Pool Water Level Monitors - At least one water level monitor shall normally be operable at all times. One water level monitor at a time may be taken out of service for maintenance purposes but shall be returned to service as soon as practicable.
At any time when both spent fuel pool water level monitors are inoperable, the water level shall be visually checked at least once each day. The monitors shall be set to annunciate a low level condition whenever the water level in the Spent Fuel Storage Pool drops below elevation 10 feet, 8 inches. Operation of the spent fuel storage pool water level monitors shall be functionally tested monthly. The level monitors shall be calibrated and the alarm setpoints verified qually. 3
- 6. f Onsite Environmental Monitorino Stations - The discharge canal continuous sampler shall normally be operated continually.
Composite samples shall be analyzed weekly (sample intervals not to exceed 200 hours) when the sampler has been operating. If the sampler is inoperable, dip samples shall be taken. Average and maximum activity and concentrations shall be reported annually. Dip R3 samples shall not be used in determination of average and maximum concentrations. Onsite dosimeter stations shall be monitored at least quarterly. Average and maximum dosimetry values will be reported annually. Ground water shall be monitored quarterly for ground water level and ! total filterable and non-filterable alpha, beta, and gamma (activity. Average and maximum values will be _ reported annually.
- 7. % se e r g _J 73 4
l t i 1 V-4 .5 l 1742S/00 K . Revision / l
3'N5CRTLl(
- 6. Onsite Environmental Monitorina Stations
- a. The discharge canal continuous sampler should normally be operating. Composite samples.shall be analyzed weekly when the sampler has been operating. -If the sampler is . inoperable, dip samples shall be taken. Average and maximum activity and concentrations shall be reported annually. Dip samples shall not be used in determination of average.and maximum concentrations.
i
- b. .Onsite dosimeter. stations shall be monitored at. i least quarterly. Average.and maximum dosimetry.
values will be reported annually. l i
- c. The groundwater monitoring wells shall be !
q sampled. quarterly for total gross alpha, total ' gross beta, total gamma activity, and tritium. Average and maximum sample results shall be prepared annually. A report will be submitted within 30 days if any.of the parameters _ listed below are exceeded: Parameter Level Basis Gross Alpha 15 pCill Drinking Hater Standard Gross Beta 50 pCi/1 Drinking Hater Standard l Tritium 3 x 10-5 pCi/mi 1% of .10 CFR 20, l Appendix B, 1 Table II, Column 2 I Gamma Emitters --- 1% of 10 CFR 20, Appendix B,. Table II, Column 2 i for Individual l Isotopes I 3121M
krysERT 5 ;
- 7. Sealed Source Leak Testina
- a. Each sealed source containing radioactive j material in excess of 100'microcuries of beta-and/or gamma- emitting material. or 10 microcuries of. alpha ' emitting naterial shall be tested for. leakage and/or contamination.
If the test reveals the presence of contamination in excess of 0.005 microcuries of removable contamination, the source shall be immediately removed from-service and decontaminated, repaired or: disposed of in accordance with Commission regulations. A report shall be prepared and submitted to the Regional Administrator, U.S.-Nuclear Regulatory _ Commission, Region V, within 30 days of the date the leak test result (greater than 0.005- , microcuries) is discovered. The report shall i specify the source involved the test results, and corrective action taken. Records of leak test results shall be kept in units of microcuries,
- b. Test Requirements - Each sealed source shall be tested for leakage and/or contamination by the !
licensee or other persons specifically ' authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries,
- c. Inspection and Tests - Each sealed source described in a. above (excluding startup sources and fission detectors previously subject to core flux) shall.be tested for leakage and/or ;
contamination as follows: (1) Sources in Use - At least once per 6 months i for all sources containing radioactive i material, other than hydrogen 3, with a half-life greater than 30 days and any form other than gas. (2) Stored Sources Not in Use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test.date shall be tested prior to being placed into use. 3121M l
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'3T- 7
VI. HASTE DISPOSAL SYSTEMS A. DESIGN FEATURES
- 1. Liauid Radioactive Haste System - Contaminated or potentially contaminated liquid waste shall be collected in one of the following Haste Collection Tanks or Sumps:
o Turbine Building Drain Tank - 3,000 gallon capacity o Reactor Equipment Drain Tank - 500 gallon capacity o Reactor Caisson Sump - 50 gallon capacity o Radwaste sump - 250 gallon capacity OPERABLE 75 If the Radwaste Discharge Process Monitor is Operable, the contents of the Reactor Caisson Sump may be automatically pumped to'the l outfall canal if periodic sample results determine that the water is - not contaminated and contamination is not suspected. Otherwise, the Caisson Sump shall be pumped to the Liquid Radwaste Treatment Facility. The contents of the remaining waste collection tanks or sumps shall be pumped to the Liquid Radwaste Treatment Facility. The Liquid Radwaste Treatment System shall consist of the following principal equipment: o Haste Receiver Tanks (3) - 7,500 gallon capacity each o Treated Haste Hold Tank (2) - 7,500 gallon capacity each o RS Radwaste r>1:cronsBed filters un (2) - 50 Toyrn m& A Radwaste cyc o Hixed De% #m capacit" c:d (mtma mineralized - 20 gpm nominal capacity o Radwaste Concentrator and auxiliaries - designed to concentrate 7,500 gallons per week o Shielded Concentrated Haste Storage Tanks (2) - 5,000 gallons capacity each Minimum treatment for any waste batch shall consist of filtration. Where further treatment is required, the following methods shall be available: o Removal of radioactivity by ion exchange o Concentration of radioactivity by evaporation (the concentrated slurry shall be stored in the Concentrated Haste Storage Tanks for ultimate off-site disposal) i l VI-1 3 1742S/00 K Revision 7
- 2. Solid Radioactive Waste System - Spent demineralized resin shall be sluiced to a shielded tank of 10,000-gallon capacity for.long term storage before ultimate off-site disposal The excess liquid from this tank shall be drawn off periodically and treated in the liquid i waste treatment facilities. '
i Other solid radioactive wastes shall be packaged and stored on-site ; for ultimate disposal off-site at an authorized disposal facility. ; Generally, solid radioactive wastes will be stored in either the ' 1,200 cubic foot underground vault or in the waste storage building. i B. OPERATING LIMITS AND REQUIREMENTS
- 1. Liould Radioactive Waste System
- a. Discharae Limits - Radioactive waste discharges to Humboldt Bay shall not exceed the limits given in 10 CFR 20, Appendix B, i Table II, column 2, on an instantaneous basis. l
- b. Stored Inventory - The radiological inventory of wastes within the liquid radioactive waste treatment system shall not exceed 800 Ci.
- c. Water from the Reactor Caisson Sump shall be sampled and analyzed monthly for total alpha, beta, and gamma activity.
Average and maximum values shall be reported annually.
- d. Each batch of wastes shall be sampled and analyzed before release to the Discharge Canal,
- e. Prior to starting a radioactive waste discharge, it shall be verified that the radioactive waste discharge line is connected to a unit with at least one circulating water pump in operation.
- f. Outdoor T mti - The radiological inventory of wastes within outdoor tanks that are not capable of retaining or treating tank overflows shall not exceed 0.25 Ci.
- 2. Solid Radioactive Waste System I
- a. Stored Inventory - The radiological inventory of wastes within I the solid radioactive waste system shall not exceed 500 C1.
- b. Haste Disoosal . Disposal of solid waste to a licensed burial '
site shall be performed in accordance with the requirements of 10 CFR, Parts 20, 61, and 71, and other applicable requirements for transportation and disposal.
- c. Process Control Proaram - Prior to shipment to a licensed burial site, liquid waste will be processed (e.g., solidified or absorbed) in accordance with a process control program which specifies acceptance criteria, test batch frequency, and remedial actions.
VI-2 1742S/00 K Revision 1
(
- 3. Gaseous Effluents Gaseous effluents shall not result in offsite ground level )
concentrations exceeding the limits.given in 10 CFR 20, Appendix 8 Table II, column 1, on an instantaneous basis. I
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l i VI-3 1742S/00 K Revision 1 i _ _ _ _ _ _ _ _ _ - - - - - - - - - _ - - _ - - - - _ _ - - _ . _ -- - . - . - - - - - - - - . - d
1 l VII. ADMINISTRATIVE CONTROLS A. RESPONSIBILITY The Plant Manager shall have the overall onsite responsibility for ; activities associated with Unit 3. He shall be accountable for adherence I to the operating limits and requirements contained in these Technical i Specifications. He shall delegate these responsibilities to other specified members of the Plant staff during his absence. B. OFFSITE ORGANIZATION j The offsite organization for plant management and technical support shall i be as shown in Figure VII-1. C. PLANT ORGANIZATION The basic plant staff organization shall be as shown in Figure VII-2. l
- 1. Requirements for the Shift Ooeratina Organization
- a. A minimum five-man operating shift organization shall be i utilized at the plant. The five-man shift is directed by a l Shift Foreman. In addition to the Shift Foreman, the other i four normal shift positions involved in the operation of Unit 3 )
are as follows: ! o Senior Control Operator o Control Operator l o Assistant Control Operator o At least one Auxiliary Operator
- b. At least one Certified Fuel Handler (CFH) shall be on-site when fuel is in the Spent Fuel Storage Pool.
- c. The Unit 3 Control Room shall be continuously manned or, as an ;
alternate, audible and visual annunciation of all alarms in ! Unit 3 shall be provided at a continuously manned control station in Units 1 and/or 2. This may be a common annunciator for all such alarms,
- d. Scent Fuel Handlina - Spent fuel shall only be handled under the following conditions:
o Spent fuel handling operations shall be under the direct supervision of a member of the plant management staff who is a Certified fuel Handler. VII-1 1742S/00 K Revision 2
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1 f E O R CR L A F NO C N F A S E A TM N Af NVI ER I NM T S L N TE A E PA NP r HR T M A U I CO EF N S e M A M mw i0 L a4 P o T< ?c 2 l l SR l V NO e r OS N Y u _ I TV I T E TE I g I AR FM RC i F U R I RE H E EP SR C O PU O E F OS F S i T N N R OR A RRI ET L E OE C E PE 1 RIN NWUI I EODG N EG WN _ SPON RE OE R P P O GT NA NI N I DL NA A D I [ ACR R \ R O I E ( T \ l I LG NCLI AONE C E I OG S ED MI N E HA CR e[ "
l l i 1 o At least one Certified Fuel Handler shall be present at the ) location of each fuel movement. I
- 2. Plant Staff Qualifications The minimum qualifications for members of the plant staff shall be the following:
- a. Plant Manager l l
(1) Ten years of responsible power plant experience, of which 1 1 year shall be nuclear power plant experience. A maximum l of 4 years of the remaining 9 years of experience may be , fulfilled on a one-for-one time basis by academic training ' in an engineering or scientific field generally associated with power production. (2) Certified Fuel Handler in accordance with the Humboldt Bay Power Plant (HBPP) certified fuel handler training program.
- b. Supervisor of Operations (1) Eight years of responsible power plant experience of which 1 year shall be nuclear power plant experience. A maximum of 4 years of experience may be fulfilled on a one-for-one time basis by academic training 'an an engineering or scientific field generally associated with power production.
(2) Certified Fuel Handler in accordance with the HBPP certified fuel handler training program.
- c. Power Plant Engineer (Technical Manager)
(1) Bachelor's degree or the equivalent in an engineering or scientific field. (2) Four years in responsible positions related to power generation, of which 1 year shall be nuclear industry experience. (3) Thorough knowledge of radiation and criticality safety requirements and practices, including safety requirements specifically related to maintenance and operations under radioactive contamination conditions. (4) Certified Fuel Handler in accordance with the HBPP certified fuel handler training program.
- d. Senior Chemical and Radiological Engineer (Radiation Protection Manager)
(1) Bachelor's degree or the equivalent in engineering or a scientific field including some formal training in radiation protection. VII-4 1742S/00 K Revision 2
(2) At least 5 years of professional experience in applied radiation protection. (A master's degree may be considered equivalent to 1 year of professional experience and a doctorate may be considered equivalent to 2 years of professional experience where course work related to radiation protection is involved.) At least 3 years of this experience should be in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations. (3) Specialized knowledge of health physics, thorough knowledge of radiation and criticality requirements and practices, and knowledge of related regulatory requirements and practices.
- e. Supervisor of Maintenance (1) Seven years of responsible power plant experience or applicable industrial experience, of which a minimum of 1 year shall be nuclear power plant experience. A maximum of 2 years of the remaining 6 years of power plant or industrial experience may be fulfilled by satisfactory completion of academic or related technical training on a one-for-one tine basis.
(2) Thorough knowledge of safety requirements specifically related to mair,tenance under radioactive contamination conditions.
- f. Quality Control Supervisor (1) Five years of responsible power plant experience or applicable industrial experience, of which a minimum of 1 year shall be experience in the nuclear field. A maximum of 2 years of the remaining 4 years of power plant or applicable industrial experience may be fulfilled by satisfactory completion of academic or related technical training on a one-for-one time basis.
(2) Thorough knowledge of nuclear materials handling, safeguards, and quality assurance methods and procedures.
- g. Shift Foreman (1) High School diploma or equivalent.
(2) At least 4 years of power plant experience-including at least 1 year of nuclear power plant experience. (3) Certified Fuel Handler in accordance with the HBPP certified fuel handler training program. VII-5 1742S/00 K Revision 1
- h. Certified Fuel Handler i (1) High school diploma or equivalent. ;
1 (2) At least 1 year of experience at HBPP. ! (3) Satisfactory completion of HBPP certified fuel handler training program. NOTES: Nuclear experience includes experience at HBPP during ; operations, or during the SAFSTOR period. ~ An individual may be assigned to any of the above positions without meeting the above requirements if a sufficient number of other per. sons who meet those requirements are assigned to the plant on a. full-time basis to assist the individual until the minimum qualifications are met.
- 3. Fire Protection Procram j
- a. The Plant Manager is responsible for the fire protection program. A member of the Engineering Staff serves as Fire Marshal with responsibilities for periodic evaluation of equipment provided for fire fighting, brigade training, and !
maintaining a current and effective fire protection program. 1
- b. At least three members of the shift operating organization shall be trained members of the fire brigade. These individuals shall be available to respond in the event of a j fire emergency in the unit. The Fire Brigade shall not include any personnel required for other essential functions during a ,
fire emergency. I i
- 4. Trainina i
- a. A training program shall be administered to certify members of !
the Plant staff as fuel handlers. The training program shall include the following: (1) Reactor theory (as it is applicable to storage of spent reactor fuel) (2) Spent fuel handling and storage equipment - design and operating characteristics (3) Monitoring and control systems (4) Radiation protection (5) Normal and emergency procedures (6) Administrative controls applicable during SAFSTOR period Successful completion of the training program shall be certified by the Plant Manager or his delegate. VII-6 ' 1742S/00 K Revision 1
- b. The Fuel Handler Certification Training Program shall include a continuing requalification program which shall include training in each of the above areas'on at least.a 2-year cycle.
- c. A training program for the Fire Brigade shall be maintained under the direction of the Fire Marshal and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.
- d. An initial training =d r;trair.ir+ program shall be administered for radiation and process monitors (RPMs) which D will include the following:
(1) Nuclear technology (2) Plant design and operation (as related to SAFSTOR conditions) (3) Chemistry (4) Radiochemistry (5) Emergency plan and procedures D REVIEM AND hsmaayew#"cyck, #"'/
- 1. Plant Staff Review Committee
- a. Purpose The Plant Staff Review Committee (PSRC) shall meet on a regular basis for the purpose of reviewing overall operating and maintenance experience; proposed changes and tests; adequacy of procedures; and other matters which may have a bearing on nuclear or radiological safety at the plant.
- b. Membership The PSRC shall be composed of members of the Plant Staff who have responsibility in the areas of 1) operations,
- 2) electrical maintenance, 3) mechanical maintenance,
- 4) instrument and control maintenance, 5) radiation protection,
- 6) nuclear engineering, and 7) quality control. Minimum membership shall include:
o Plant Manager (Chairman) o Supervisor of Operations o Supervisor of Maintenance o Power Plant Engineer o Senior Chemical and Radiological Engineer o Quality Control Supervisor
- c. Alternates (1) In the absence of a regular member, the Chairman may designate an alternate from the plant staff to carry out' review functions.
3 VII-7 Revision 2' 1742S
(2) The Chairman shall designate a regular member to serve as chairman in his absence,
- d. Meeting Frequency Once per calendar quarter and at other times at the discretion of the Chairman.
- e. Quorum A Quorum shall consist of four regular members or three regular members and an alternate.
- f. Responsibilities (1) The PSRC shall review the following items prior to implementation for the purpose of determining if a change in the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59 is involved and shall render such determinations in writing:
I a) Proposed tests and experiments determined by a Committee member to have nuclear safety significance. I b) Proposed changes or modifications to Unit 3 systems or l equipment. I c) Proposed normal, abnormal, and emergency operating l procedures, maintenance procedures, security procedures, administrative procedures, and other procedures determined by a Committee member to be significant to the maintenance of Unit 3 in SAFSTOR. d) Proposed changes to approved procedures of the type described in item c. above. e) Proposed changes to the Technical Specifications. (2) The PSRC shall periodically review: a) Approved procedures of the type described in item 1.c above for currency and applicability, b) Operating, maintenance, and surveillance testing experience to ensure safe and efficient operation of the Unit and to determine if changes to equipment or procedures are needed. (3) The PSRC shall investigate any violation of these Technical Specifications and prepare and forward a report to the Vice President, Nuclear Power Generation and the General Office Nuclear Plant Review and Audit Committee (GONPRAC) covering their evaluation and recommendations to prevent recurrence. VII-8 1742S/00 K Revision 1
(4) The Plant Staff Review Committee shall conduct a biennial review of: a) The Plant Security Plan and implementing procedures to determine the need for changes in the Plan or its implementing procedures. b) The Site Emergency Plan and its implementing procedures to determine the need for changes in the Plan or its implementing procedures.
- g. Authority (1) The PSRC shall recommend to the Plant Manager approval or disapproval of proposals reviewed under sub items f. (1) through (3) above.
(2) The PSRC's determinations shall be rendered in writing with regard to whether or not a proposed change or test or other such matter which has been reviewed involves an "unreviewed l safety question" as defined in 10CFR50.59(c) or a change in the Technical Specifications. , (3) In the event of disagreement between Committee members on a matter affecting nuclear or radiological safety, a i conservative course as determined by the Plant Manager shall be followed. Records of such disagreements shall be included in the meeting minutes as described in item h. below and distributed promptly. ]j
- h. Records Minutes of each PSRC meeting shall be prepared and maintained at tne Plant. Copies of minutes shall be sent to the Vice President, Nuclear Power Generation and to GONPRAC.
- 2. General Office Nuclear Power Plant _ Review and Audit Committee,
- a. Purpose The General Office Nuclear Power Plant Review and Audit Committee (GONPRAC) shall function to provide independent review and audit of designated activities in the areas of:
(1) Nuclear power plant operations (2) Nuclear engineering l (3) Chemistry and radiochemistry (4) Metallurgy . (5) Instrumentation and control ' (6) Radiological safety (7) Mechanical and electrical engineering (8) Quality assurance practices VII-9 1742S/00 K Revision 1
i 1 i GONPRAC shall report to and advise the' 0;;;the t' ice President-fict'itie sad Eh trk ";;egiue Oe.eleg.ei.t on those areas of ff3 responsibility specified in Items (2g) and (2p$ below, la
- b. Composition
.GONPRAC shall be composed of the following:
o Vice President, Nuclear Power Generation (Chairman) o Assistant to the Vice' President, Nuclear Power Generation (Vice Chairman) o Manager, Nuclear Operations Support (Member)' o . Manager, Nuclear ~ Engineering and. Construction' Services
-(Member) o Manager, Station Construction'(Member) o Chief Mechanical and Nuclear Engineer (Member) o Manager, Quality Assurance (Member) o Director, Nuclear Administration and Support Services'-
(Member) o Director, Nuclear Regulatory Affairs.(Member)
- c. Alternates All alternate members shall be appointed in writing by the .
'. GONPRAC Chairman to serve on' a temporary basis; however, no more than two-alternates shall participate as voting J. embers in i GONPRAC activities at any one time.
- d. Consultants Consultants shall be utilized as determined by the GONPRAC Chairman to provide expert advice to GONPRAC.
i
- e. Meeting Frequency-GONPRAC shall meet at least once per 6 months.
- f. Quorum I L
A minimum GONPRAC quorum necessary for the performance of- ! GONPRAC review and audit functions of these Technical Specifications shall consist of the Chairman or Vice Chairman ; and at least four GONPRAC members, including ~ alternates. l i
'1742S/00_ K Revision [ I
- g. Review GONPRAC shall review:
(1) The safety evaluations.for (1) changes'to procedures, equipment or systems, and (2) tests or experiments completed under the provision of.10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question. (2) Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR-50.59. (3) Proposed tests or. experiments which involve an unreviewed safety question as defined in 10 CFR 50.59. (4) Proposed changes to Technical Specifications or this Possession-Only License. (5) Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance. (6) Significant operating abnormalities or deviations from normal and expected performance of Unit equipment, j l (7) Event (s) requiring written notification to the Commission. (8) All recognized indications of an unanticipated deficiency 1 l in some aspect of design or operation'of structures, systems, or components that could affect nuclear safety. 1 (9) PSRC reports and meeting minutes. I
- h. Audits Audits of Unit activities shall be performed under the cognizance of GONPRAC. These audits shall encompass:
(1) The conformance of Unit operation to provisions contained ! within the Technical Specifications and applicable'11 cense conditions - at least once per 12 months, (2) The performance, training, and qualifications of the entire- . Unit staff - at least once per 12 months. (3) The results of actions taken to correct significant deficiencies occurring in Unit equipment, structures, i systems, or method (s) of operation - at least once per 6 months. : I VII-11 1742S/00 K Revision 1-1 _ _ _ - _ _ = _ _
(4) The performance of activities required by the Quality Assurance Program at least once per 24 months. (5) The emergency plan and implementing procedures - at least once per 24 months. (6) The Security Plan and implementing procedures - at least once per 24 months. (7) The Fire Protection Program and implementing procedures - i at least once per 24 months. (8) An independent fire protection and loss prevention program l inspection and audit shall be performed at least once per i 12 months utilizing either qualified offsite license personnel or an outside fire protection firm. (9) An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant - at least once per 36 months.
- i. Records I
Records of GONPRAC activities including minutes of meetings, I reports of reviews, and audit reports shall be prepared, approved, and distributed as required by the approved GONPRAC . Charter. ) E. PROCEDURLS
- 1. Detailed written procedures, including applicable checkoff lists and instructions, shall be established, implemented, and maintained for significant activities associated with the maintenance of Unit 3 in SAFSTOR, including:
- a. Fuel handling operations (including removal and reinsta11ation of the Spent Fuel Storage Pool Cover).
- b. Normal startup, operation, and shutdown of systems and components which are required during the SAFSTOR period.
- c. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components.
u %nek
- d. Emergency conditions involvin pote .!: : ;c"" release Sof 73 radioactivity [oncj %c po wcs to implemed[%t EmugbefM,
- e. Abnormal and emergency operation of all systems and components which are required to maintain the SAFSTOR condition of the Plant.
- f. Plant Security Pla implement n se nc (CC (Y W E3 ,
h, Cahbahon eE MS bon h5cb 50 OtmMNfbC compbanct 17425/00 K a es se mm. , Revision 7
I I l I l
- 2. All procedures described in item 1 above, and changes thereto, shall be reviewed by the PSRC and approved by the Plant Manager prior to )
implementation, except as provided in items 3 and 4 below. J
- 3. Rules shall be established which provide methods by which temporary changes can be made to approved procedures, including the l designation of those persons authorized to approve such changes.
Temporary changes, which clearly do not change the intent of the 3 approved procedure from the standpoint of nuclear safety, may be l approved by two members of the plant management staff, at least one of whom is a Certified Fuel Handler. Such changes shall be documented and, if appropriate, incorporated into the next revision i of the affected procedure.
- 4. In the event of an emergency not covered by an approved procedure, 1 operations personnel shall be instructed to take action so as to I minimize personnel injury and damage to the facility.
F. SITE EMERGENCY PLAN The Site Emergency Plan shall provide the necessary prearrangement and organization of personnel to deal effectively with emergencies at the Plant so as to minimize radiation exposure to Plant personnel and the general public. The plan shall describe the specific duties of Plant personnel in the event of an accigent or any unplanned incident producing high radiation levels. Periodic prill shall be performed to ensure that y all Plant personnel are thoroughly fam iar with the plan. G. OPERATIONAL TESTING crerases descrded m de 6FWVqcncy ga n. Testing of system components, monitors, and other equipment to which these Technical Specifications apply shall be as described in l Sections III through VI. Each operational test shall be performed within the specified time interval with: ] l
- 1. A maximum allowable extension not to exceed 25% of the test interval.
- 2. A total interval time for any three consecutive test intervals not I to exceed 3.25 times the specified test interval.
j Appropriate tests shall also be performed following maintenance on the:e systems which could impair their operation. H. REPORTING REQUIREMENTS In addition to the applicable reporting requirements of 10 CFR, the following identified reports shall be submitted: wnal Adm,mskkg MC* Rape 1(uhha Ccqy de NfQg> An annual report to thegU .S. "uclear Regulatory Cc=issieri,- li;;hington, D.C., shall describe the results of the environmental. R3 and facility radiation surveys, the status of the facility, and an evaluation of the performance of spcurity and surveillance measures kn#un 90 dap of' hong i of each (pr, VII-13 3 1742S/00 K Revisionf l l
- 2. Non-Routine Reports-
- a. The NRC Operations Center shall be notified of emergency and non-emergency events in accordance with 10 CFR 50.72.
~
- b. Reportable events shall be reported in accordance with 10 CFR 50.73.
- 3. Semiannual Effluent Release Report Paragraph (a)(2) of 50.36a, " Technical Specifications on Effluents From Nuclear Power Reactors," of 10 CFR, Part 50 requires that a report be submitted to the Commission within 60 days after January-1 and July 1 of each year which specifies the quantity of each of the principal radionuclides released to unrestricted areas in-. liquids and gaseous effluents during the previous 6 months of_ operation.
The information submitted in the semiannual effluent release report shall be in accordance with Regulatory Guide 1.21 (Revision 1), dated June 1974 and Regulator.y Guide 4.1 April 1975 The ,Sepannd Ehnt '&Jc25c evision o/f shd1),bedated sent
- C 73 NAC 11 in $c NfC *DocwneA
- 4. RymalReoorts Snecial kmonsskat%cemivol'Dc5 icm LT, a Q a C l
If the calculated dose to.any member of the general public exceeds the 40 CFR 190 limits, a special report shall be made to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region V, within 30 days. This report shall include an analysis of the estimated. dose received by a member of the public from. uranium fuel cycle sources for the applicable consecutive 12-month' period. The report shall also describe the corrective actions planned to l reduce subsequent exposures and to prevent recurrence of the event.- The special report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and include the information specified in 40 CFR 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until Staff action on the request is complete. I. RECORD RETENTION
- 1. All records and logs relative to the following areas shall be retainedforatleast4 years: 73_
- a. Records and logs of normal SAFSTOR operations.
- b. Records and logs of principal maintenance activities,-including inspection, repair, substitution, or replacement of- principal' items of equipment pertaining to systems "i p bdacrtlM ,.
VII-14 3 1742S/00 K Revision p '
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- c. Reportable Occurrence Reports
- d. Records of periodic checks, inspection and/or calibrations performed to verify that surveillance requirements are being met.
- e. Records of radioactive shipments.
- f. Records of sealed source leak test and results.
- g. Records of annual physical inventory of all source material of ,
record. g, 13 l.
- 2. All records relative to the following areas shall be retained for the duration of SAFSTOR: J
- a. Records and prints of changes made to the Plant.
- b. Records of spent fuel inventory, transfers of fuel, and assembly histories.
- c. Records of plant radiation and contamination surveys.
- d. Records of offsite environmental monitoring surveys. 3
- e. Records of radiation exposure for all plant personnel, j including all contractors and visitors to the plant, in ,
accordance with 10 CFR 20. ' Records of radioactivity in liquid and gaseous wastes released
\\ f.
to the environment.
\@ Records of tests or experiments associated with the spent fuel storage.
- h. Records of changes made in operating procedures. 1 Records of training and qualification for current members of
$'V. the plant staff.
--tr "ccordi vi iniervice inspee44cas perfer.ued pursuant to these-D Tec4m+ cal-Sper mcatMnL-h.JW" Minutes of meetings of the PSRC and the GONPRAC.
/ J( Records of Quality Assurance activities required by the SAFSTOR Ouality Assurance Plan.
3 p/ Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 4hc _10 CFR, P:rt 50.59r- FH5R. VII-15 3 1742S/00 K Revision /
J. RADIATION PROTECTION PROGRAM Radiation control procedures shall be prepared, approved and adhered to, and made available to all plant personnel. These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20. The radiation protection program shall be organized to meet the requirements of 10 CFR 20. K. HIGH RADIATION AREA
- 1. Pursuant to paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the
" control device" or " alarm signal" required by paragraph 20.203(c)(2), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mr/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance 'of special work permits (SHPs). Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the SHP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mr/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the ,
radiation dose rate in the area; or !
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset i, integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for l providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified.
- 2. In addition to the requirements of Specification VII.K.1, areas accessible to personnel with radiation levels greater than 1000 mr/h at 45 cm (18 in.) from the radiation source or from any surface ;
which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or Health Physics supervision. Doors'shall remain locked except during periods of access by personnel under an approved SHP which shall T VII-16 1742S/00 K Revision 1 ;
specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the SWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protectior. procedures to provide positive exposure control over the activities being performed within the area. l l l VII-17 1742S/00 K- Revision 1
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