ML19248D817
| ML19248D817 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 07/13/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19248D815 | List: |
| References | |
| NUDOCS 7908170528 | |
| Download: ML19248D817 (14) | |
Text
.
UNITED STATES
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't NUCLEAR REGULATORY COMMISSION h
WASHINGTON. D. C. 20555 VM gv f
- e PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO._50-133 HUMBOLDT BAY POWER PLANT UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.18 License No. OPR-7 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas and Electric Company (the licensee) dated October 20, 1978, as supplemented January 24, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applicatinn, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
79081 70 f20
-9E 248 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph C.2. of Facility Operating License No. DPR-7 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.18, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as c' the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Thomasfe.kppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: July 13, 1979 og 74g n
ATTACHMENT TO LICENSE ANENDMENT NO. 18 FACILITY OPERATING LICENSE NO. DPR-7 DOCKET NO. 50-133 Revise Appendix A as follows:
Remove the following pages and replace with identically numbered pages:
III-8 III-9 III-ll V-8 VI-7a IX-4a IX-5 IX-8 IX-9 IX-10 IX-19 Changes on the revised pages are shewn by marginal lines.
III-9 b.
The e ystet, may be taken out of service for the purpose of maintenance er testing but shall be returned to service as soon as practical.
c.
Leskage rates shall be determined on e continuousabasis. If evalua-tion of leakage rate trend data from the crnitoring system indicates that leakage is increasing, efforts shall be made to locate and correct the source (s) of leakage.
d.
If extrapolation of the monitoring system measured leakage rate exceeds the coerational leak. tee rate, corrective repair shall be made as soon es practical. Leakage rate extrapolation from menitoring system pressure shall be based on the Nove=ber 1965 tests results as given below:
Extrapolation Factor from Test Pressure Test Pressure to 10 osig Dry Well 20 inches of water 4.3 Suppression Chamber 10 inches of water 8.9 e.
The maxi =um partial pressure of dry gas shall not exceed the following limits during operation of the leakage rate monitoring system:
(a) Dry Well 16.0 psia (b) Suppression Cha=ber 15.7 psia 5.
Penetration Closure Testing 4.
Access Penetrations - Leakage tests shall be made on the dry well top and bottom heads, and the suppression chamber access penetrations by pressurizing to 25 psig with air between the double "0" ring seals.
These tests shall be made prior to each power operation startup if these heads have been opened and reclosed. The sum of the leaka ge rates f. rom these penetration closures shall be less than 157. of the eperational leakage rate limit given in this Section.
b.
Isolatten '!alves - During petiods of sustained power operatica, the nsin s team, coolant cleanup supply and return, and emergency condenser stea= supply cotor operated isolatica valves shall be exercised l
(partial}y closed and reopened) at least once each conth.
I During each regularly scheduled refteling outage, isolation valves shall be tested for proper operation and tightness as described below.
Prior tc the tightness tests, tne isolation valves shall be closed by the norcal code of actuation vLthout any preliminary exercise or adjustments.
The =rin stea=, coolant :lennu.s ru ply and return, and emergency con-denser steam supply and condensate return oter operated isolation valves shall be tested fnv:icCly f or prcper automatic operation (dcr.cribed in S ecti:n '!I). r. d 0.:: tiosure vithin the design ti=e specitied in A-1 of this Secticn. All other manual, motor operated, air operr.:ed ard solenoid opera:ed f rolation valves shall be tested for preper operation.
c.
me A end:ent No. 18 b
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III-11 operated on recirculation at least once each mcnth during periods of power operation. The auto =atic initiation of the system shall be functionally tested during each regularly scheduled refueling outage.
One of the plant fire protection system pu=ps may be te=porarily removed because of maintenance at any ti=e during operation, provided that both core spray pu=ps are operable, except that the diesel-povered fire pump cust be operable whenever the emergency propane-povered generator is required to be operable (refer to Section VI-B. 7. a. )
c.
Reactor Vent Valves - The reactor vent valves shall be functionally tested during each regularly scheduled refueling outage.
8.
Refueline Building Testing - The. refueling building shall be tested to demonstrate that the air in-leakage rate is less than 134 cfm when the building is under a negative pressure of at least k inch of vater.
Testing shall be perfor=ed during refueling or power operation at the following times:
(a) prior to removal of the reactor head folleving power
, operation, (b) af ter any opening of the railroad door, and (c) af ter main-tenance which =ay have affected any of the refueling building penetration closure seals.
If not required for these reasons, the test shall be per-formed at least once each conth.
l 9.
Refueline Building Ventilation System - A functional test of the automatic operation of the refueling building ventilation. system as described in A-5 of thisSection III shall be conducted prior to each regularly scheduled refueling cutage.
- 10. _Containcent Recuirements - The follovipg definitions shall apply to con-tainment requirements:
1.
Reactor System Containment - The condition eristing when the reactor vessel and associated syste=s are closed so as to provide containment of irradiated fuel within the reactor core.
b.. Pressure Sueoression Containment - The condition existing when all dry well and suppression chatber penetrations are in the positions listed in Tables III-l and III-2.
Operating limits and requirenents for pressure suppression contain=ent are that (1) the caster ventilation control switch normally shall be set in the "Nor=al Operation" position, (2) the suppression pool water level shall be in the range of 17.0 to 19.0 feet (5.0 to 7.0 feet vent pipe sub=ergence)6 (3) the suppression pool bulk water te=perature shall be less than 90 F and, (4) the te=perature of the gas entering the dry well cooler (s) shall be less than 175 F.
'5<*
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D, O' Am.n am, n t. N o.
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V-8 shall only be done af ter the core shutdown cargin has been decon-etrated. Until such ti=e as the rod and/or drive has been replaced and checked for proper operation, the master reactor svitch shall be in the " servicing" position.
g.
Abnormal Behavior of the Control Rod System - In the event of any abnor=41 behavior of the control rod system, an Lczediate and thor-ough investigation shall be made to deter =ine the cause and safety significance of the occurrence. The reactor shall be shut down unless it is determined by the investigation that any nalfunction which has occurred does not impair the ability to control the reactor and that the i= pair =ent of the perfor=ance of additional components of the control rod systes is not i==inent.
3.
Liquid Poison System - The liquid poison system shall be available for operation at all times during refueling and power operation. The reactor shall be shut down i==ediately in any situation where the poison worth of the system is known to be less than the =ini=u= permissible value or where the ability of the syste=3 to inject pois >n into the reactor is in doubt.
Operating li-its shall be. as follows:
m Minimum ustble solution boron content (to be annunciated by low level alarm),
pounds of boren 100 Maximus solution concentration, % by weight modium pentaborate 40 Minimum solution temperature above saturation tecperature (to be annunciated by lov te=perature alarm). #F 5
Minimum nitrogen pressure (to be annen-ciated by low pressure a! arm), psig 13 00 The poison injection valves shall be exercised at least once each centh during periods of refueling and power operation.
When the reactor is in the hot, operating condition, local manual operatica of poision injection valves during exercising, which would prevent remote control rcom operation of the systen, shall be per=1ssible provided the. personnel perf orcing the tests are in com=unication with the control room.
Amen d= en t No. 18
$Ok cD"J 9
I
.iu
VI-7a i
(a) Description of the effort, progress, and schedule relating to restoration of the normal sources cf power.
(b) Description of the increased surveillanee and adminis-trative controls in eff ect to assure the safety of continued operation of Unit No. 3, and (c) Description and saf ety significance of ano=alous per-formance of any syste=s or components relating to Unit No. 3 or its operating power sources, unexplained changes in operating variables of the reactor, and indication of a change in the integrity of the containment or the primary coolant boundary.
Any significant changes of the information supplied in (a), (b), or (c) shall be immediately transmitted to I6E Region V.
b.
The ability of Unit Nos. 1 and 2 to carry house load in the event that these units are separated f rom the system shall be tested at least cace every five years (one of the units shall be tested each 2-years).
l Such tests shall nor= ally be performed under initial conditions of rated load on the Unit. An in-service trip of a unit from initial conditions of greater than 50% load shall also be censidered as a test.
c.
The ability of the 2.4 kV bus of Unit No. 3 to auta=atia lly transfer from its house transfor=er to the Plant 60 kV bus shall be tested for proper transfer operation during each regularly scheduled refueling outage.
d.
The transfer of the emergency 480. volt a-c shall be tested for proper operation as specified in VI.A.7b at least once each month. This l
transfer shall be functionally tested with all loads connected so as to simulate emergency operation during each regularly scheduled refuelirig outage, e.
The ability of the d-c systen to supply the e=ergency short-term load for the safe shutdown of the reactor shall be tested during each regularly scheduled refueling outage.
me o A=endment No. 18 b '9,i.
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IX La b.
Membership The Plant Staff Review Ccc=ittee shall be co=pesed of the following members of the Plant Staff who have respcosibility in the areas of 1) operati:ns, 2) electrical maintenance, 3) cechanical maintenance,
- 4) instrument and control maintenance, 5) radiation protection, 6) nuclear engineering, and 7) quality ecntrol.
Plant Superintendent (Chair an)
Supervisor of Operaticos Power Plant Engineer Power Production Engineer (Nuclear Engineer)
Chemical and Radiat. ion Protection Engineer quality Control Supervisor c.
Alternates
- 1) In the absence of a regular =e=ber, the Chair =an
=ay designate an altemate frce the plant staff to carry out review functions.
- 2) The Chairman shall designate a regular member to serve as chair an in his absence.
Amendment No. 18 bU ri 255
IX-5 d.
Meeting Frequency Chee per calendar month and at other times at the call of the
- Chairman, e.
Quorum A quorum shall consist of four regular members or three regular members and an alternate.
f.
Responsibilities
- 1) Review proposed nor=al, abnormal and emergency operating procec.ures, maintenance procedures and proposed changes thereto; and any other proposed procedures or changes thereto involving the safety related aspects of safety related equipment.
- 2) Review all proposed tests and experiments that affect nuclear safety.
~
- 3) Review proposed changes to the Technical Specifications prior to their imple=entatien.
kl Review of all proposed changes er modifications to safety related systems or equipment.
- 5) Investigation of any violation of the Technical Specificat'.ccr.:
and preparation and f avarding of a report to the Manager of Steam Generaticn covering their evaluation and recocuendaticas to prevent recurrence.
- 6) Review plant operating and caintenance experience to assure safe and efficient operation of the Unit.
7)
Biennial review of the Plant Security Plan and implementing l
procedures to determine the need for changes in the Plan or its implementing procedure.
- 8) Biennial review of the Site E=ergency Plan and its implementing }
procedures to determine the need for changes in the Plan or its implementing procedures,
g.
Authority
- 1) Reco= mend to the Plant Superintendent approval or disapproval of proposals reviewed under item f. (1) thru (k) above.
A=endment No. [' 18 P, '
- h.
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IX-8 c) Proposed changes in the technical specifications or license amendments relating to nuclear safety prior to imple=entation of the change or amend =ent.
d) Violations, deviations, and reportable occurrences such as:
(1) Violaticos of applicable codes, regulation s~,
orders, technital specificati cns, license requirements, or internal procedures or instructions having nuclear saf ety significance on facility operaticn; (2) Significant operating abnor=alities, deviations frc= normal or expected perfor=ance of plant safety-related structures, syste=s, or co=ponentr,;
and (3) All events vY.ch are required by regulations or Teebnical Specifications to be reported to the NRC in writing within 2k hours.
Review of events covered under this paragraph shall include timely reporting to appropriate =e=bers of Campany canagement on the results of any investigaticus
=ade, and the reco==endaticns resulting fro: such investigaticns to prevent or reduce the probability of recurrence of the event.
e) Reports and neeting cinutes of the Plant Staff.
Review Co==ittee.
f) Cc cunicaticns with the NRC concerned with the nuclear power plants.
g) Any otber =atter involving safe operatico ef. the Co=pany's nuclear power plants which a Co==ittee =e=ber dee=s appropriate for Ccc=ittee consideration, or which is referred to the Ccc=ittee by a Plant Superintendent, A General Office department, er the President'.s Nuclt.ar Adviscry Ccc=ittee.
- 2) It is a function of the Ccc=ittee to provide Ccepany manage =ent with assurance that nuclear plant operations ccnfor= to laws and regulations, license provisions, and internal Cc=pany rules and policy related to nuclear safety. To accceplish this, the Cc==ittee shall:
a) Review and evaluate audits conducted by those Cc=pany Departments having auditin6 responsibility. The overall audit program shall be in confor=ance with the requirerer.ts of Section 4.5 of ANS1 NIS.7 - 1976 as amplified by Section C.4 of Revision 2 of Regulatory Guide 1.33 dated February 1978.
A=end en t No. jd,18
,e' s
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n-9 b) At its discretica, perfor= audits itself e= ploying
[
either the entire Ccc=ittee or parts thereof, as appropriate.
c) Perfom or otherwise arrange for an independent fire protectico and loss preventica inspectico and audit at least ennually utilizing either qualified off-site Company personnel or an outside fire protectico fir =.
d) Perfom or othervise arrange for an audit of the Plant Fire Protection Progra= anc i=ple=enting procedures at least once per 24 =caths.
e) Arrange for an inspection and audit of the fire protection and less prevention progra= by an outside qualified fire consultant at intervals no greater than 3 years.
f) Perfom or otherwise arrange for acco=plishing other auditing activities as =ay be directed by the Senior Vice President, Engineering and Ccostruction.
g) Recce=end =anagement approval for e= ploying censult-ants to conduct audits whenever necessary.
h) Report its findings, eccelusions and reco==endaticns to Cccpany =anagement.
1.
Records Records of GGiPRAC activities shall be prepared, approved and distributed as indicated below:
- 1) Written ninutes of each =eeting shan be prepared, fomally approved and distributed to Co==ittee = embers, to the Cc=pany officers to who= the C" ttee = embers report, and to the President's Euclear Advisory CeMttee.
Copies of the minutes shall be retained as specified in Subsection J.2.1.
- 2) Reports of audits and other Cc==ittee activities shall be distributed to 3enior Vice President, the Vice President-Electric Operations, the President's Nuclear Advisory C o==i t t e s., other affected =anage=ent personnel, and others as directed.
E.
LIPCRTABLE OCCUPJtHICES ACTIGi The following action shall be taken in the event of a reportable occurrence:
1.
The Co==issico shall be notified and/or a report submitted pursuant to the requirements cf Section IX.1.2 of these Technical Specificaticos.
A=end=ent J.o. M)/fb 8 qc n
n n ; :3 2
0
IX-10 c.
Actions to be taken to corrcet specific and f oreseen potential malfunctions of systec,s or cocponents, including suspected primary system leaks and abnor:21 reactivity
- changes, d.
Emergency conditions involving potential or actual release of radioactivity.
Abnormal and emergency operation of the reactor and of e.
all systems and coeponents.
f.
Plant Security Plan implementation.
2.
All procedures described in 1. above. and changes thereto, shall be reviewed by the Plant Staf f Review Com=ittee and approved by the Plant Superintendent prior to i=plecentation, except as provided in 3. and 4. below.
3.
Rules shall be established which provide methods by which temporary changes to approved procedures can be made, includtng the designation of those persons authorized to approve such changes. Temporary changes, which clearly do not change the intent of the approved procedure from the standpoint of nuclear saf ety, may be approved by two me=bers of the plant management staff, at least one whom holds a senior operator license.
Such changes shall be docu=ented and, if appropriate, incorporated in the next revision of the af f ected procedure.
4.
In the event of an et.crgency not covered by an approved procedure, operations personnel shall be instructed to take action so as to minimize personnel. injury and da= age to the f acility.
G.
SITE EMERCENCY PLAN The Site Emergency Plan shall provide the necessatf prearrangement
~
and organization of personnel to deal ef fectively with emergencies at the Plant so as to minimize radiation exposure to Plant personnel
~
and the general public. The plan shall describe the :pecific-duties of Plant personnel in the event of an accident.or any unplanned incident producing high radtation levels.
Periodic drills shall be C]
D perfor=ed to assure that all plsnt personnel are ~ thoroughly f amiliar with the plan.
- M H.
OPERATIONAL TESTIN0 CF NUCLEAR SAFEGUAP.DS SYSTE'.S M3 Procedures f or tes ting o f saf e ty system components, monitors, and other equipment having a potential safeguard functica shall be as described in Sections I'I through VIII. These tests and the frequency CS of testing are listed in Table IX-1. Operational Testing of Nuclear Eg -q Safeguards Systems.
Each Operational Test shall be perf ormed f
gpd/
vithin the specified time interval with:
rd 1.
A maximum allovable extension not te exceed 25~ of the test ALI T '
interval.
W H7 2.
A total interval tioe for any 3 consecutive *.est intervals not bd to exceed 3.25 ti=es the specified test in t e rv.11.
py Appropriate tests shall also be perfor=ed following =aintenance on u
these systecs which cald impair the r operation.
Amendment No. M ) ( N hb h
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