ML20128H460
| ML20128H460 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/30/1984 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20128H415 | List: |
| References | |
| FOIA-84-658 NUDOCS 8505300519 | |
| Download: ML20128H460 (11) | |
Text
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JUL 3 01984 MEMORANDUM FOR:
Harold R. Denton, Director, Office of N'uclear Reactor Regulation FROM:
James P. O'Reilly, Regional Administrator
SUBJECT:
READINESS FOR LICENSING - GRAND GULF This memorandum is to advise you that Region II has reviewed and inspected outstanding items at Grand Gulf and conclude that the facility and operating staff are ready for a full power license.
The inspection activities have included operational readiness team inspections, Standby Service Water Basin modifications, Technical Specifications change requests and results of the low power test program.
Based on our inspections and evaluations, all items addressed on Attachment I to license NPF-13 have been completed satisfactorily to support a full power operating license.
Enclosure (1) of this memorandum addresses each item on Attachment I and references the documents that support the finding that these license conditions have been satisfied.
It is our understanding, that NRR has action on Items 1.c and 3, (concerning control room leak tightness), and that they have been satisfactorily met and will be addressed in supplement No. 6 to the safety evaluation report.
Accordingly, Region II supports the issuance of a full power license for Grand Gulf.
2 James P. O'Reilly
Enclosure:
Status Listing of Attachment 1 Items 8505300519 841102 PDR FOIA DELL 84-658 PDR
JUL : 0 n:e 4 m
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This attachment identifies certain preoperational tests, systert denons tra tion s and other items dich must be cmpleted to the Commission's satisfaction.
The licensee shall not proceed without written confirmation ' rom NRC that the following itens have been ccrnpleted.in accordance with. the conditions and schedule set forth below.
1.
Prior tb initial criticality the licensee shall complete to the satisfaction of the NRC the following open itms and construction deficiencies:
a.
Resolve issue regarding installation of automatic sprinklers in the auxiliary building which differs from the SER.
(81-48-01) 8256c b.
Resolve issue regarding the lack of fire protection systems in certain areas as required by the,FSAR.
(82-34-01) 8256c Resolve issue regarding maintain [ng Ahe control room at greater
$y c.
Ed than 1/8 inch water pressire. RESOLVED IN MP6L LETTER AEcM 83/0333 g2.
(6/16/83)....TO BE ADDRESSED IN SUPPLEMENT NO.6 TO SER QiRR ACTION )
d.
Determine cause of short in stator of division II diesel generator.
(82-14) 8327c e.
Resolve issue regarding failure of relay in division I diesel generator voltage control.
(82-15) 8321c f.
Resolve issue regarding uninsulated leads used in GE type if4A relay in RHR pump control circuitry.
(82-17) 8242c g.
Resolve issue regarding defective threads on CRD houstng support rods.
(82-05) 8259c h.
Modifications to RCIC turbine mounting studs and lube oil piping support. 8259C 2.
Prior to exceeding 5 percent power, the licensee shall conplete to the satisfaction of the NRC the following NRC Bulletin item, open items, construction deficiencies and TMI-2 Action Plan Ites:
a.
The requirements of NRC Bulletin 79-8U-18 audibility problens encountered on evaluation alars systems. 833'oc b.
Completion and evaluation of the following preoperational tests.
e 8337c (1) Feedwater Control Systa (1C34PT01) 8329c (2) Traversing Incore Probe (1C51PT03) 8329c (3) Loose Parts Monitor Syste (IC87PT01) 83 33c (4) Main Steam Line Radiation Monitoring System (1017PT01) t O
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2-I 8329C (5) Off Gas Radiation Monitoring Syste (ID17PT02) 8337c (6)
Main Steam Isolation Yalve Leakage Control System (1E32PT01) 8320c (7) Liquid Radweste System (SF17PT02)
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8320c (8) Solid Radweste System (SG18PT01) 8320c (9) Off Gas System (IN64PT01) c.
Completion and evaluation of the following acceptance tests.
8337C (1) Main and Reheat Stem Syste (1N11AT01) 8337c (2) Auxiliary Steam Syste (SN12AT01) 8337c (3) Heater Vents and Drains Syste (IN23AT01) 8337c (4) Turbine Control Fluid System (IN32AT01) 8337c (5) Main and Reactor Feed Puw.ps Turbine Seal Stem and Drains (IN33AT01) 8309C (6) Lube Oil Storage and Conditioning (1N34AT01) 8337c (7) Turbine Lee Oil System (1M34AT02) 8351c (8) Generator / Generator Controls and Supervisory (IN41AT02) 8329C j
(9) Seal Oil System (IN42AT01) 8337c (10) Generator Cooling System (IN43AT01) 8337c (11) Hydrogen and Carbon Dioxide System (IN44AT01) e-8337C (12) Exciter /Thyristor Voltage Regulator (1N51AT01) 8337C (13) Circulating Water System (1N71AT01) e337c (14) Make-up Water Treatment Syste (SP21AT01) 8329c (15) Main Transfonner System (1R14AT01)
/
(16)' 22KV Isophase Bus Ventilation Syste (1,R24AT01) 8329C 83290 (17)
Isophase Bus Ventilation Heat Load (1R24AT01)
REQUIRES FULL 8324c (18) Cathodic Protection Systa (1R62AT01) 8329c (19) Turbine Building Ventilation System (1V41AT01) e t
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d.
Completion and evaluation of the following special tests.
8429C (1)
Balance of Plant Piping Vibration Monitoring (Portion prior to 5% power) (1C885T04) 83490.(2)
Balance of Plant Piping Expansion Monitoring (Portion prior to 5% power) (1C885T05) SUFFICIENTLY COMPLETE TO OPERATE ABOVE $*
8351c (3) Verification Test of Vibration, Expansion and Temperature Sensors on Balance of Plant Piping (1C885T06) 8429c (4) Transient Test Equipment Verification (Portion prior to 51 power) (IC885T07)
Demonstrate full site personnel assembly and accountability.
e.
(81-44-08) 8257c f.
Complete testing of radweste disch'arge line.
(82-21-07) 8258c '
g.
Verify seismic adequacy of Bettis air actuators furnished with certain Henry Pratt butterfly valves.
(81-44) 8419C h.
Evaluate seismic qualification of standby diesel generator startup air canpressor 3/8 inch sensor line.
(82-04) 8244c 1.
Resolve inadequate flow in standby service water to RCIC
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system.
(82-21) 8419C j.
Resolve issue related to Division 111 Diesel Generator room ventilation systs being inoperable.
(82-25) 8261c k.
Resolve failure of RWCU isolation valve not closing on Standby Liquid Control Systen initiation.
(82-26) 8261c 1.
Resolve problem of Hiller actuators not fully closing valves on slow loss of air.
(82-28) 8261c l
i m.
Resolve problen of excessive corrosion in Dikker safety relief valve actuators.
(82-29) 8331c Determine effect of error in Bechtel's jet impingement analysis.
n.
(82-30) 8251c Detitrutne cause of corrosion on terminal boards in Rosmont o.
t transmitters.
(82-23) 8327c p.
Resolve probJams of yoke failures on Bettis actuators used on 24" Henry Pratt butterfly valves.
(82-32) 8261c q.
Resolve missing vacutan breakers on vent lines for the scre discharge volume. 8330c ~
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-t r.
Implementation of the follo.ing TMI-2 action plan (NLREG-0737) requirements.
'8334c (l')
II.F.1.1 Modify procedures for accident mon'itoring ins trumenta tion.
8334c (2)
II.F.1.2.a Install noble gas ef fluent monitor.
8334c (3) 11.F.1.2.b Provide monitoring for Iodine particulate /
gaseous ef fluents.
8334c (4)
I I.F.1. 2.c Install containment high range radiation nonitors.
(5)
Complete other NtREG-0737 items required for full power unless specifically exempted by the license.
All TMI Actions Items required for the issuance of a full power license have been completed.
The.close out date and associated report can be.found on the ".IE TMI ACTION ITEM COMPUTER STATUS f1 STING." As indicated on this status listing, only six (6) items remain open; five of which are not required until startup following the first refueling outage., The sixth item (II.F.2.4) concerns the adequacy of instrumentation for detection of inadequate core cooling. License Condition 2.c.(44)(f), which required the licensee to sub-mit a report addressing the analysis performed by the BWR Owners Group re-
'garding this item, has been satisfied. Any determination 'for additional in-strumentation or modifications resulting from NRR review of this report will be addressed in a later supplement to the SER and will be completed on a.
schedule acceptable to the staff.
3.
Prior to March 1,1984, the licensee shall submit additional information as specified in MP&L letter dated August 23, 1983, that is acceptable to the NRC in support of the calculations of control room operator doses due to control room inleakage under accident conditions.
Specifically, such in.
g formation shall include the results of plant specific wind tunnel tests to establish an appropriate value for the concentration coefficient (K) '
2 used in establishing X/Q values and the results of other analyses performed f
g f
in support of a limit on control room leakage higher than 263 cfm but less 2
than or equal to 590 cfm.
In the interim, based on a measured containment N
leak rate of 0.072%/ day, a control room envelope leak rate of up to 590 cfm
,is acceptable. MP&L* HAS SUBMITTED ADDITIONAL INFORMATION....TO BE ADDRESSED IN SUPPLEMENT NO.6 TO SER(NRR ACTION)
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-MEMORANDUM-FOR: Darrell G. Eisenhu't, Director, Division of Licensing, NRR
~. FROM :
Richard C. Lewis, Director, Division of Reactor Projects
SUBJECT:
READINESS FOR LICENSING - GRAND GULF This - memorandum is to advise you' that-Region II has reviewed and inspected outstanding items at Grand Gulf and conclude that the facility and operating staff are readf. for. a full power ' license.
The inspection activities have included ~ operational readiness team inspections, Standby Service Water Basin modifications, Techncial Specifications change requests and results of the low power test program.
Based on our inspections and evaluations all items
-addressed on Attachment.1 to license NPF-13 have been completed satisfactorily
+
to. support a full power operating license.
Enclosure (1) of this memorandum addresses each item on Attachment 1 and references the documents that support
.the finding that these license conditions have been satisfied.
It is our understanding, based on telephone conversations with the NRR licensing project manager, that items 1.c and 3, (concerning control room leak tightness, have beenisatisfactorily met and will be addressed in supplement No. 6 to the safety evaluation report.
I
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- 2 According, Region II' supports.the issuance of a full power license; for Grand Gulf.
- -r Richard C. Lewis
Enclosure:
Status Listing of Attachment 1 Items I
6 9
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g p
g I
~
Exctn.et Rr (1)
A 1A: @.* 1 TC L10!N5! Wrr.33 This attachment identifies certain preoperational tests, syster-de.onstrations and other items which must be cepleted to the Commission's satisfaction.
The. licensee shall not proceed without written confirmation frort NRC that the following itens have been ceple'ted in~ accordance wi th the ' conditions and '
~
schedule set forth below.
1.
Prior th. initial criticality the licensee shall complete to the satisfaction of the NRC the following open items and construction deficiencies:
a.
Resolve issue regarding installation of automatic sprinklers in the auxiliary building which differs from the SER.
(81-48-01) 8256c b.
Resolve issue regarding the lack of fire protection systems in certain areas as required by the FSAR.
(82-34-01) 8256c i.
Wn c.
Resolve issue regarding maintaining Ahe control room at greater Ed than 1/8 inch water pressure. RESOLVED IN MP&L LETTER AECM. 83/0333' g z.
(6/16/83)....To BE ADDRESSED IN SUPPLEMENT NO.6 TO SER 4
d.
Determine cause of short in stator of division II diesel generator.
(82-14) 8327c Resolve issue regarding failure of relay in division I diesel e.
generator voltage control.
(82-15) 8321c f.
Resolve issue regarding uninsulated leads used in GE type M4A relay in RHR pump control circuitry.
(82-17) 8242c g.
Resolve issue regarding defective threads on CRD housing support rods.
(82-05) 8259c h.
Modifications to RCIC turbine mounting studs and lube oil piping support. 8259C 2.
Prior to exceeding 5 percent power, the licensee shall emplete to the satisfaction of the NRC the following NRC Bulletin item, open items, construction deficiencies and TMI-2 Action Plan Items:
The requirements of NRC Bulletin 79-8U-18 a,udibility problems i
a.
l encountered on evaluation alarm systems. 833'oc b.
Completion and evaluation of the following preoperational tests.
/
8337c (1) Feedwater Control System (1C34PT01) 8329c (2) Traversing Incore Probe (1C51PT03) 8329c (3) Loose Parts Monitor System (1C87PT01) 83 33c (4) Main $ team Line Radiation Monitoring System (1D17PT01) e O
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--w--.-r
_,r.,-,,,_,,-~,-.,%--,.-ww.-.,-
c.,,,,e,.%,.,
--r,,,,,,,-,-,w we n w,,. w
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1 8329C (5) Off Gas Radiation Monitoring System (1017PT02) 8337c (6) ' Main Steani ' Isolation Valve Leakage Control System (1E32PT01) 8320c (7) Liquid Radweste System (SF17PT02)
~
8320c (8)
Solid Radwaste System (SG18PT01) 8320C (9) Off G4s System (IN64PT01) c.
Completion and evaluation of the following acceptance tests.
8337c (1) Main and Reheat Steam Syste (1N11AT01) 8337c (2) Auxiliary Steam System (SN12AT01) 8337c (3) Heater Vents and Drains Syste (IN23AT01) 8337c (4) Turbine Control Fluid System (IN32AT01) 8337c (5) Main and Reactor Feed Pumps Turbine Seal Steam and Drains (IN33AT01) 8309c (6) Lube Oil Storage and Conditioning (IN34AT01.)
8337c (7) Turbine Lube 011 System (IN34AT02) 8351c (8) Generator / Generator Controls and Supervisory (1N41AT02) 8329C (9) Seal 011 System (IN42AT01) 8337c (10) Generator Cooling System (IN43AT01) 8337c (11) Hydrogen and Cart >on Dioxide System (IN44AT01) e-8337c (12) Exciter /Thyristor Voltage Regulator (IN51AT01) 8337c (13) Circulating Water System (IN71AT01) e337c (14) Make-up Water Treatment System (SP21AT01) 8329c (15) Main Transformer System (1R14AT01) 8329c (16) 22KY Isophase Bus Ventilation System (1,R24AT01) 83290 (17) Is0 phase Bus Ventilation Heat Load (1R24AT01)
REQUIRES FULL 8324c (18) Cathodic Protection System (1R62AT01) 8329C (19) Turbine Building Ventilation System (1V41AT01) 9 4
e
1 2-d.
Completion and evaluation of the follomang special tests.
8429c (1)
Balance of Plant Piping Vibration Monitoring (Portion prior
~
to 5% power) (1C885T04) 83490,(2) Balance of Plant Piping Expansion Monitoring (Portion prior
~
to 5% power) (1C885T05) surricIENTLY COMPLETE TO ' ENTER TCl 8351c (3) Verification Test of Vibration Expansion and Temperature Sensors on Balance of Plant Piping (1C885T06) 8429c (4) Transient Test Equipment Verification (Portion prior to Si power) (1C885T07) e.
Demonstrate full site personnel assably and accountability.
(81-44948) 8257c f.
Complete testing. of, radweste disch'arge line. '(82-21-07) 8258c g.
Verify setsmic adequacy of Bettis air actustors furnished with certain Henry Pratt butterfly valves.
(81-44) 8419C h.
Evaluate seismic qualification of standby diesel generator startup air, compressor.3/8 inch sensor line.
(82-04) 8244C 1.
Resolve inadequate flow in standby service water to RCIC system.
(82-21) 8419c
~j.
Resolve issue related to Division III Diesel Generator room ventilation systs being inoperable.
(82-25) 8261c k.
Resolve failure of RWCU isolation valve not closing on Standby Liquid Control Syste initiation.
(82-26) 8261c 1.
Resolve proble of Hiller actuators not fully closing valves on slow loss of air.
(82-28) 8261c T.
W) Resolve problen of excessive corrosion in Dikker safety relief
~
valve actuators.
(82-29) 8331c n.
Determine effect of error in Bechtel's j.et impingement analysis.
(82-30) 8251c o.
Determine cause of corrosion on terminal boards in Rosmont transmitters.
(82-23) 8327c Resolve problems of yoke failures 24" Monry Pratt butterfly valves., on Bettis actuators used on p.
(82-32) 8261c q.
Resolve missing vacuus breakers on vent lines for the scrm discharge volume. 8330c O
se
4.
Implementation of the following TMI-2 action plan (NtREG-0737) r.
requirements.
8334C (l')
II.F.1.1 Modify procedures.for accident monitoring instrumentation.
(2)
!!.F.1.2.a Install noble gas effluent monitor.
8334C (3) II.F.1.2.b Provide monitoring for lodine particulate /
8334C gaseous effluents.
8334C (4) I I.F.1. 2.c Install containment high range radiation monitors.
(5)
Complete other NIREG-0737 items required for full power unless specifically exempted by the ifcense.
All TMI Actions Items required for the issuance of a full power license have been com'pleted.
The close.out date and associated report can be found on the "IE TMI ACTION ITEM COMPUTER STATUS LISTING." As indicated on this status listing, only six (6) items remain open; five of which are not required until startup following the first refueling outage.. The sixth item (II.F.2.4) concerns the adequacy of instrumentation for detection of inadequate core cooling. License Condition 2.c.(44)(f), which required the licensee to sub-mit, a report addressing the analysis performed by the BWR Owners Group re-garding this item, has been satisfied. Any determination 'for additional in-strumentation or modifications resulting from NRR review of this report will be addressed in a later supplement to,the SER and will be completed on a.
schedule acceptable to the staff.
3.
Prior to March 1, 1984, the licensee shall submit additional information as specified in MP&L letter dated August 23, 1983, that is acceptable to the NRC in support of the calculations of control room operator doses due to control room inleakage under accident conditions. Specifically, such in-L
@l formation shall include the results of plant specific wind tunnel tests C*
to establish an appropriate value for the concentration coefficient (K)*
g 21 used in establishing X/Q values and the results of other analyses performed
!l in support of a limit on control room leakage higher than 263 cfm but less gl than or equal to 590 cfm.
In the interim, based on a measured containment gl leak rate of 0.072%/ day, a control room envelope leak rate of up to 590 cfm
,is acceptable. MP&L'HAS SUBMITTED ADDITIONAL INFORMATION....TO BE ADDRESSED IN SUPPLEMENT NO.6 TO SER, b
~
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.I 9
.