ML20052C442
| ML20052C442 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/12/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20052C443 | List: |
| References | |
| DPR-35-A-060 NUDOCS 8205040815 | |
| Download: ML20052C442 (14) | |
Text
.
- "*4 f
UNITED STATES i
NUCLEAR REGULATORY COMMISSION h
,j i
WASHINGTON. D. C. 20555 e
- a BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR P0'3ER STATION AMENDMENT TO FACILITY OPERATING LICENSE bPR-35 cne o 1.
The Nuclear Regulatory Commission (the Commission) has found that:
I A.
The application for amendment by Boston Edison Company (the licensee) dated October 15, 1981,. 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 application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be l
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; I
, 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.
2.
Accordingly, the license is amended by changes to the Technical Spec-l ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
B.
Technical Specifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8205040815 820412 PDR ADOCK 05000293 P
d 2
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t
/
f fl Domenic B. Vassallo, Chief
..i Operating Reactors Branch #2 Division of Licensing
Attachment:
l.
Changes to the Technical
.l Specifications
.i Date of Issuance: April 12,1982
'2
~
'1.
i
{<
I i
I i
f I
l l
l t
.. _ _ _. _ ~. -. _.. ~. _. _ _ _... _,.
ATTACliMENT TO LICENSE AMENDMENT NO.
60 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment Number and contain a vertical line indicating the area of change.
Remove Replace 137a-137a 137b 137b 137c 137c 137d' 137d 137e 137e 137f 1379 137h 1371 151a 151a 224 224 i
h l
i i
l l
LIMITING CONDITION FoR OPERATION I
SITAVEILLANCE REOUIREMENT 3.6.I Shock Suppressors (Snubbers) 4.6.I Shock Sunoressors (cnubbers) 1.
During all modes of opera-The following surveillance tion except Cold Shutdown requirements apply to all and Refuel, all safety-hydraulic and mechanical related snubbers listed in snubbers listed in Tables Table 3.6.I(a) and 3.6.I(b)
- 3. 6.I(a) and 3.6.I(b).
- j shall be operable except as noted in 3.6.I.2 through The required visual inspec-
~l 3.6.I.3 below.
tion interval varies inverselv i
with the observed cumulative An Inoperable Snubber is a number of inoperable snubbers properly fabricated, installed found during an inspection.
and sized snubber which can-Inspections performed before not pass its functional test.
that interval has elapsed may be used as a new Teference Upon determination that a snu6her point to determine the n' ext' is either improperly fabricated, inspection. However, the
- 3 installed or sized, the correc-results of such early inspec-tive action will be as specified tions performed before the 1
for an inoperable snubber in original time interval has Section 3.6.I.2.
elapsed may not be used to lengthen the required inter-2.
Fmm and after the time that a val.
snubber is determined to be in-operable, replace or repair the Number of snubbers found in-snubber during the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, operable during inspection or and initiate an engineering evalu-during inspection interval:
ation to determine if the com-ponents supported by the snubber (s) subsequent were adversely affected by the-Inocerable visual Inspec-inoperability of the snubbers and Snubbers tion Interval to ensure that the supported component remains capable of 0
18 Fonths
- 25%
meeting its intended function in i
12 Months i 25%
the specific safety system in-2 6 Ponths 25%
volved.
3,4 124 Days t 25%
5,6,7 62 nays 25%
Further corrective action for this 8 or more 31 Davs snubber, and all generically sus-ceptible snubbers, shall be The required inspection inter-determined by an engineering val shall not be lengthened evaluation more than one step at a time.
3.
From and after the time a snubber snubbers.may be categorized is determined to be inoperable, in two groups, " accessible" improperly fabricated, improperly or " inaccessible" based on installed or improperly sized, if their accessibility for inspec-the requirements of Section(s) tion during reactor operation.
3.6.I.1 and 3.6.I.2 cannot be met, These two groups may be in-then the affected safety system, spected independently accord-or affected portions of that ing to the above schedule.
system, shall be declared inoper-able, and the limiting condition 1.
Visual Inspection Acceptance for that system entered, as criteria appropriate.
A. visual inspections shall verify:
137a Amendment No. /p 60
LIMITING CONDITIOff FOR OPE?aTION l
SURVEILL.CCE PlQUIREMENT 4.6.I Shock Suppressors (Snubbers) 1.
That there are no visible in-dications of damage or tspaired 4
Snubbers day be added to, or operability.
removed from, per 10 CFR 50.59, 2.
Attachments to the founda-safety related systems without tion or support structure prior License Amendment to are such that the func-Table 3.6.I(a) or 3.6.I(b) tional capability of the provided that a revision to snubber is not suspect.
,the appropriate Table is in-cluded with the next license B. Snubbers which appear INOPER-amendment request.
ABLE as a result of visual inspections may be determined OPERA 3LE for the purpose of establishing the next visual' inspecti n-interval provided that:
1.
The cause of the rejection-1 is clearly established and remedied for that particulac. +
snubber, and
'2.
The affected snubber is functionally tested, when' necessaty, in the as found condition and determined OPERABLE per specifications app icable, 4.6.I.2.C., as 4.6 I.2.B.
3.
For any snubber determined inoperable per specifica-tion 4.6.I.2, clearly establish the cause of re-jection and remedy the prob-lem for that snuober, and any generically susceptible snubber.
2.
Functional Tests (Hvdraulic and Mechanical Snubbers)
A.
Schedule At least once per operating cycle (18 months), a representa-tive sample (10% of the total of each type: hydraulic, mechanical) of snubbers in use in the plant shall be functionally testea, either in place or in a bench test.
For each snubber that does not meet the functional test
' acceptance criteria of 137b Amendment No gp 60
e LIMITING CONDITION FOR OPERAIION I
SURVEILLANCE REOUIRE.E i!
l 4.6.I Shock Suppressors (Snubbers).
Specification 4.6.I.2.B. or 4.6.I.2.C, as applicable, an additional 10% of that type of snubber shall be functionally tested.
4 B.
General Snubber Functional Test Acceptance Criteria.
(Hydraulic and Mechanical)
The general snubber functional I
test shall verify that:
l.
Activation (restrain-ing action) is achieved within the specified
.i range of velocity or
'I acceleration in both l
tension and compression.
1 2.
Snubber release, or bleed-fi rate, as applicable, where required; is within the specified range in l
compression or tension.
For snubbers specifi-cally required not to i
displace under contin-ucus load, the ability of the snubber to with-stand load without dis-placement shall be veri-fied.
C.
Mechanical Snubbers Functional f
Test Acceptance Criteria The mechanical snubber functional test shall verify that:
f
)e 1.
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Drag force shall not have inc-reased more than 50% since the last functional test.
3.
Snubber Service Life Monitoring A.
5 record of the service life 137c Amendment No. 60
LIMITING CONDITION FOR OPERATION SL*RVEILLANCE REQUIREMENT 4.6.I Shock Suppressors (Snubbers) of each snubber, the date at which dhe designated service life commences and the instal-lation and maintenance records on which the designated service life is based shall be maintained.
B.
At least once per gycle, the in-
~
stallation and maintenance records for each snubber listed in Tables 3.6.I(a) and 3.6.I(b) shall be reviewed to verify that the in-
. dicated service life hasinot been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life i
will be exceeded priorstc the.
l next scheduled snubber service life review, the snubber service life shall be reevaluated, or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditiening shall be indicated in the records.
C.
This Snubber Service Life Moni-toring Program shall become ef fective July 1,1982.
II t t 8
i 137d I
Amendment No. 60
Table 3.6.1(a)
N SAFETY RELATED !!YDRAULIC S110CK SUPPRESSORS (SNUBBERS)
,a Snubber No.
location Elevation Snubber in liigh Snubbers Snubbers Snubbers s"
Radiation Area Especially Inaccessible Accessible
~
Dur*ng Shutdown Difficult to During Normal During Normal Remove Operation Operation M
t X (Drywell) 2 SS-1-10-1 Main Steam Line 42' SS-1-10-2 Main Steam Line 42' X (Drywell)
S5-1-10-3 Main Steam Line 42' X (Drywell) j SS-1-10-4 Main Steam Line 42' X (Dryvell);
SS-1-10-5 Main Steam Line 42' X (Drywell)
SS-1-10-6 Main Steam Line 42' X (Drywell)
SS-1-10-7 Main Steam Line 42' X (Drywell)
SS-1-10-8 Main Steam Line 42' X (Drywell)
SS-1-10-9 Main Steam Line 42' X (Drywell)
SS-1-10-10 Main Steam Line 42' X (Drywell)
SS-1-10-Il Main Steam Line 42' X (Drywell)
SS-1-10-12 Main Steam Line 42' X (Dryvell)
SS-6-10-6 Feedwater Sys.
41' X (Drywell) 55-6-10-7 Feedwater Sys.
41' X (Drywell)
SS-6-10-8 Feedwater Sys.
44' X (Drywell)
SS-6-10-9 Feedwater Sys.
41' X (Drywell)
SS-6-10-10 Feedwater Sys.
44' X (Dryvell)
SS-10-30-1 RilR System 52' X (Drywell)
SS-10-20-2 RllR System 52' X (Drywell)
SS-10-20-3 RilR System 52' X (Dryvell)
SS-10-20-4 RHR System 52' X (Drywell)
SS-10-%-5 RHR System 24' X (Drywell)
SS-10-30-6 RHR System 24' X (Drywell)
SS-10-20-7 RHR System!
24' X (Drywell)
SS-10-20-8 RllR System 24' X (Drywell) i SS-10-3-9 RllR System 87' X (Drywell)
SS-10-3-10 RliR System 90' X (Drywell)
SS-2-20-1 Re'cir. System 42' X
X (Drywell)
SS-2-20-2 Recir. System 42' X
X (Drywell)
SS-2-20-3 Recir. System 42' X
X (Drywell)
SS-2-20-4 Recir. System 42' X
X (Drywell)
SS-2-30-5 Recir. System 15' X
X (Drywell)
SS-2-30-6 Recir. System 15' X
X (Drywell)
SS-2-30-7 Recir. System
'15' X
X (Drywell)
C B'
.u.2.._,_
Table 3.6.I(a) jf SAFE'IT RELATED llYDRAULIC S110CK SUPPRESSORS (SNUBBERS) g
?o f
Snubber No.
Location Elevattor.
Snubbar in High Snubbars Sr.ubb ars Sr.abbers Radiation Area Especially inaccessible Accessible During Shutdown Difficult to During Normal During Normal cS Remove Operation Operation X (Drywell)
SS-2-30-8 Recir. System 15' X
X (Drywgil)
SS-2-30-9 Recir. System 11' X
X (Drywell)
SS-2-30-10 Recir. System 11' X
X (Drywell)
S S-2-30-I l Recir. System 27' X
X (Drywell)
SS-2-30-12 Recir. System 27' X
X (Drywell)
S S-2-30-13 Recir. System 27' X
X (Drywell)
S S-2-30-14 Recir. System 27' X
X (Drywell)
SS-2-30-15 Recir. System 27' X
X (Drywell)
SS-2-30-16 Rccir. System 27' X
X (Drywell)
SS-2-20-19 Recir. System 16' X
X (Drywell)
SS-2-20-20 Recir. System 16' X
X (Drywell)
SS-2-20-21 Recir. System 19' X
X (Drywell)
SS-2-20-22 Recir. System 16' X
X (Drywell)
SS-2-50-23 Recir. System 17' X
i X (Drywell)
SS-2-20-24 Recir. System Id' X
X (Drywell)
SS-2-20-25 Recir. System 16' X
X (Drywell)
SS-2-50-26 Recir. System 16' X
?
6 J
Table 3.6.I(a) m S
SAFETY RELATED llYDRAULIC S110CK SUPPRESSORS (SNUBBERS) o Snubber No.
Location Elevation Snubber in liigh Snubbers Snubbers Snubbers 2
Radiation Area Especially Inaccessible Accessible During Shutdown Difficult to During Normal During Normal g
Remove' Operation Operation SS-6-10-1 Feedwater System 42' X (Drywell)
SS-6-10-2 Feedwater System 42' X (Drywell)
SS-6-10-3 Feedwater System 42' X (Drywell)
SS-6-10-4 Feedwater System 42' X (Drywell)
S S 10-5 Feedwater System 42' X (Drywell)
SS-13-3-1 RCIC 38' X (Drywell)
SS-13-3-2 RCIC 38' X (Drywell) 35-14-3-1 Core Spray 65' X (Drywell)
SS-14-3-2 Core Spray 65' X (Drywell)
SS-14-3-3 Core Spray 65' X (Drywell)
SS-14-3-4 Core Spray 65' X (Drywell)
SS-23-10-1 II. P. C. I.
42' 4 (Dr"well)
X (Dr'ywell)
SS-23-10-2 II.P.C. I.
42' SS-2 3-3-30 li. P.C. I.
-3' 09" y
X ll.P.C.I. Quadrant X ll. P.C. I. Quad rant SS-23-3-31 II.P. C. I.
- 3' 09" g
X 11.P.C.I. Quadrant SS-23-10-32
- 11. P. C.1.
-3' 09" a
a X ll.P.C.I. Quadrant SS-23-10-34 II. P.C. I.
-6' X ll.P.C.I. Quadrant SS-23-10-35 ll. P. C. I.
- 6' X ll.P.C.I. Quadrant SS-23-3-36 ll.P.C.I.
- 3' 09" X ll.P.C.L. Quadrant SS-23-3-37 II. P. C. I.
-3' 09" X RilR Pump Room SS-10-3-4 3 RilR
- 3' 06" SS-10-20-44 RilR
- 3' 06" X RilR Pump Room X Reactor Building SS-30-3-45 RBCCW 83'5" X Torus Compariment SS-10-10-46 RilR 6"
11-3-1-1292 CRD System of Modifications to thin Table due to changes in high radiation areas should be submitted to the NRC as part the next license amendment.
y OQ i
e
t Ng Table 3.6.I(b) k SAFETY RELATED MECllANICAL SilOCK SUPPRESSORS (SNUBBERS)
E Snubber No.
Location Elevation Snubber in liigh Snubbers Snubbers Snubbers Ha.liation Area Especially inaccessible Accessible During Shutdown Difficult to During Normal During Normal Remove Operation Operation
=
MS-S-500 M.S. Relief Line A X (Drywell)
MS-S-501 H.S. Relief Line A X (Drywell)
MS-S-502 M.S. Relief Line A X (Drywell)
MS-S-503 M.S. Relief Line A X (Drywell)
MS-S-504
'M.S. Relief Line A X (Drywell)
MS-S-505 M.S. Relief Line A X (Drywell)
MS-S-506 M.S. Relief Line A X (Drywell)
MS-S-507 M.S. Relief Line A X (Drywell)
MS-S-508 M.S. Relief Line B X (Drywell)
MS-S-509 M.S. Relief Line B X, (Drywell)
HS-S-510 M.S. Relief Line B X, (Drywell)
MS-S-511 M.S. Relief Line B X. (Drywell)
MS-S-512 M.S. Relief Line B X (Drywell)
MS-S-513 M.S. Relief Line B X (Drywell)
MS-S-514 M.S. Relief Line B X (Drywell)
MS-S-515 M.S. Relief Line B X (Drywell)
MS-S-516 M.S. Relief Line C X (Drywell)
MS-5-517 M.S. Relief Line C X (Drywell)
MS-S-516 M.S. Relief Line,C X (Drywell)
MS-S-519 M.S. Relief Line C X (Drywell)
MS-5-520 M.S. Relief Line C K (Drywell)
MS-S-521 M.S. Relie f Line C l
MS-S-522 M.S. Relief Line C X (Drywell)
X (Drywell)
MS-5-523 M.S. Relief Line C X (Drywell)
MS-S-524 M.S. Relief Line C X (Drywell)
[
e 14 9
I e
3
l Table 3.6.I(b) a SAFETY RELATED ME01ANICAL Sil0CK SUPPRESSORS (SNUBBERS) g W
Snubber No.
Location Elevationi Soutilier in liigh Snubbers Snubbers Snubbers Ra.liation Area Especially inaccessible Accer.sible m
O During Shutdown Difficult to During Norausl During !:ormal Remove Operation Operation MS-5-525 M.S. Relief Line D X (Drywell)
MS-5-526 M.S. Relief Line D X (Drywell)
MS-S-527 M.S. Relief Line D X (Drywell)
MS-5-528 M.S. Relief Line D X (Drywell)
MS-5-529 M.S. Relief Line D X (Drywell)
MS-5-530 M.S. Relief Line D X (Drywell)
MS-5-531 M.S. Relief Line D X (Drywell)
MS-S-532 M.S. Relief Line D X (Drywell)
MS-5-533 H.S. Relief Line D X (Drywell)
MS-5-534 M.S. Relief Line D X (Drywell) t
'. k 13
{ (i-4 4,
l i
e i
e
EASES:
3.6.I & 4.6.I SHOCK SUPPRESSORS (SNUBBERS)
Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal ther=al motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads. It is therefore: required that all snubbers required to protect the primary coolant system and all other safety related systems or components be operable during reactor operation.
The visual inspection frequency is based on maintaining a constant level of snubber protection to systems. The cumulative number of inoperable snubbers detected during any inspection interval is the basis for establishment of the subsequent inspection interval and the existing inspection. interval should remain in effect until its completion.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.
Gemr' ally susceptible snubbers are those which are of a specific make or model and same design features directly related to rejection of the snubber by visral he a
inapection, and are exposed to the same environmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable, an engineering evaluation is initiated, in addition to the determination of the snubber mode of failure, in order to dstermine if any safety-related component or system has been adversely affected by the,inoperability of the snubber.
Initiating this evaluation within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ensures that prompt corrective action will be afforded.
Hydraulic snubbers and mechanical snubbers may etch be treated as a different entity for the above surveillance programs.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...). The requirement to montror the snubber service life is included to ensure that the snubbers period-ically undergo a performance evaluation in view of their age and operating condi-tions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintanance of records and the snubber service life review are not intended to affect plant operat ion. Due to the number and complexity of the relevant interacting factors 'necessary to develop a comprehensive Service Life Program, this program shall become effective July 1, 1982.
151a Amendment No. 20 60
1
^
d 3.
Special Reoorts Special reports shall be submitted as indicated in Table 6.9.1.
l i;
6.10 P2 CORD RETENTION A.
The following records shall be retained for at least five years:
'{
Records of facility operation covering time interval at each power 1.
j ~;
level.
t
,i 2.
Records of principal maintenance activities, inspections, repair j
and replacement o6cprincipal items of equipment related to i
nuclear safety.us d m 3.
Reportable Occurrence Reports.
~
.l 4.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
j 5.
Records of reactor tests end experiments.
6.
Records of changes made to Operating Procedures.
7.
Records of radioactive shipments.
8.
Records of sealed source leak tests and results.
9.
Records of annual physical inventory of all source material of record.
3.
The fo11 cuing records shall be retained for the duration of the Operating License:
2 1.
Record and drawing changes reflecting facility design nodifications made to systems and equipment described in the Final Safety Analysis l,'
Report.
l l
2.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
3.
Records of facility radiation and contamination surveys.
4.
Records of radiation exposure fer all individuals entering radiation control areas.
5.
Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.6.I(a) and 3.6.I(b) including the date at which the service life commences and associated installa-tion and maintenance records.
Amendment No. 30 60 224
-