ML20052A170
| ML20052A170 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/30/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052A171 | List: |
| References | |
| TAC-10477, TAC-10478, NUDOCS 8204270519 | |
| Download: ML20052A170 (22) | |
Text
'o UNITED STATES
[
NUCLEAR REGULATORY COMMISSION c,
j WASHINGTON, D. C. 20555
?%,...../
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. DPR-66
~ 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio-Edison Company, and Pennsylvania Power Company (the licensees) dated February 11, 1982 complies with the standards and require-ments 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 an_d regulations of the Comission; C.
There is reasonable assurance (1) 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.
- 1
)
8204210519 g
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66.is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specificaticns.
3.
This license amendment is effective as of the date of its issuance.
Fp THE NUCL REGULATORY COMMISSION
(.ir
/
Steven A. Yarga, C ef Operating Reactor,q ranch #1 Division of Licens ng
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 30,1982
e*
O ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 49 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-28 3/4 7-19 3/4 7-29 3/4 7-30 3/4 7-30 3/4 7-31 3/4 7 -31 c
3/4 7-32 3/4 7-32a 3/4 7-32a 3/4 7-32b 3/4 7-32b 3/4 7-32c 3/4 7/32c 3/4 7-32d 3/4 7-32d 3/4 7-32e i
3/4 7-32e 3/4 7-32f 3/4 7-32g 3/4 7-32h 3/4 7-321 3/4 7-33 3/4 7-33 B3/4 7-6 B3/4 7-6 B3/4 7-6a 6-19 6-19 l
1 l
l.
t i
p _...
3 PLANT SYSTEMS 3/4.7.12 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.12 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.'
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.12.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.12 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
I a.
Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.
If less than two (2) snubbers are found inoperable during the first j
inservice visual inspection, the second inservice visual inspection shall be performed 12 months + 25% from the date of the first inspection. Otheraise, subsequent visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers per Inspection Period Subsequent Visual, j Inspection Period 0
18 months + 25%
1 12 months T 25%
2 6 months T 25%
3,4 124 days + 25%
5,6,7 62 days T 25%
8 oc more 31 days T 25%
The snubbers may be categorized into two groups:
those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
The inspection interval shall not be lengthened more than one step at a time.
The provisions of Specification 4.0.2 are not applicable.
BEAVER VALLEY - UNIT 1 3/4 7-26 Amendment No. 2, M 49
~
PLANT SYSTEMS SURVEILLAh'CE REQUIREMENTS (Continued) b.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of dazage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly estab-lished and remedied for that particular snubber and for other snubbers that =ay be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.12.d or 4.7.12.e, as applicable. However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
c.
Functional Tests At least once per 18 months during shutdown, a representative sample l
(of at least 10 snubbers or at least 10% whichever is less) of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.
For each snubber that does the functional test acceptance criteria of Specification 4.7.12.d l
not meet or 4.7.12.e, an additional 10 snubbers or at least 10% whichever is less i
of that type of snubber shall be functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:
1.
The first snubber away from each reactor vessel nozzle 2.
Snubbers within 5 feet of heavy equipment (valve, pu=p, turbine, motor, etc.)
3.
Snubbers within 10 feet of the discharge from a safety relief valve.
BEAVER VALLEY - UNIT 1 3/4 7-27 Amendment No. 2, YV 49
w.~.._...____.
J PLANT SYSTEMS SURVEILLANCE REQUIREMENTS '(Continued)
Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.* Tables 3.7-4a and 3.7-4b may be used jointly or separately as the basis for the sampling plan.
If a spare snubber has been installed in place of a failed snubber, the spare snubber shall be retested. Test results of this snubber may not be incluced for the re-sampling.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by trianufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.
This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
d.
Hydraulic Snubbers Functional Test Acceptance Criteri&
The hydraulic snubber functional test shall verify that:
1.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
BEAVER V ALLEY-U NIT 1 3/4 7-28 Amendment No. 7 49
- o.,
.-~
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4 e.
Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
l.
The force that initiates free movement of the anubber rod in either tension or compression is less than the specified maximum drag force.
2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
4 3.
Snubber release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
f.
Snubber Service Life Monitoring A record of the service life of each snubber, the date at which 1
the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.m.
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or will not be' exceeded prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubbec 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 reconditioning shall be indicated in the records.
O BEAVER VALLEY - UNIT 1 3/4 7-29 Amendment No, d 49
l TABLE 3.7-4a SAFETY RELATED flVDRAULIC SNUBBERS *
.5
~
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE TO REMOVE F
Q RC-IlC-1A RC RCP Cub. A 736'6" I
Yes Yes RC-IlC-2A RC RCP Cub. A 731'2" RC-itC-3A 736'6" c-5 RC-IlC-4A 736'6" RC-IlC-5A 728'2" RC-itC-6A 736'6" RC-IlC-7A 728'2" RC-IIC-8A 731'2"
~
RC-IlC-9A 766'10" RC-IlC-10A 766'10" RC-IIC-llA 766'10" R
RC-IIC-12A 766'10" a
7 RC-IlC-1 B RC RCP Cub. B 728'2" 8
RC-IlC-2B 728'2" RC-IIC-3B 731'2" RC-IIC-4B 736'6" RC-IlC-58 736'6" RC-IlC-6B 736'6" RC-IIC-7B 736'6" RC-IIC-8B 731'2" RC-IIC-9B 766'10"
"~
F RC-IIC-10B 766'10" g-RC-IlC-11B 766'10" g
RC-IIC-12B 766"10" n
E Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 proviM that safety evaluations, documentation and reportin9 are provided in accordance with 10 CFR 50.59 and that a revision to Table 3.7-4 is included with a subsequent License Amendment request.
2
~
1 TABLE 3.7-4a (Continued)
SAFETY RELATED llYDRAULIC SNUBBERS
- m5 75 m
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR llIGH RADIATION ESPECIALLY DIFFICULT g
NO.
ON, LOCATION AND ELEVATIP1 INACCESSIBLE ZONE TO REMOVE ~
F Q
RC-IIC-lC RC RCP Cub. C 731'2" I
Yes Yes RC-IIC-2C 736'2" g
RC-IIC-3C 728'2" 5
RC-IIC-4C 736'6" H
RC-IIC-5C 736'6" RC-IIC-6C 731'2" RC-IIC-7C 728'2" RC-IIC-8C 736'6" RC-IIC-9C 766'10" RC-IIC-10C 766'10" RC-IIC-llc 766'10" RC-IlC-12C 766'10" w
2 RC-IISS-5 RC REA. CONT. BLDG.
716' I
Yes Yes y
4, RC-HSS-6 716' RC-IISS-7 716' RC-IISS-8 716' RC-IISS-9 716' RC-IISS-10 716' Ril-llSS-123 RHR 699' A
No No Ril-flSS-124 699' SI-ilSS-110.
SI 708' SI-HSS-lll 708' S1-1155-119 697' SI-IISS-120 697' l
SI-ilSS-108 708'
@e Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that safety evaluations, documentation and reporting are provided in accordance with 10 CFR 50.59 and s
g that a revision to Table 3.7-4 is included with a subsequent License Amendment request.
i
TABLE 3.7-4a (Continued)
SAFETY RELATED flYDRAULIC SNUBBERS
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE TO REMOVE F
Q SI-ilSS-103 SI REA. CONT. BLDG.
695' A
No No e
SI-HSS-101 705' s;;
SI-ilSS-104 705' Ril-llSS-106 RHR 704' Yes Ril-flSS-109 704'
~
Ril-llSS-110 704' RH-ilSS-ll2 704' RC-IISS-11 RC RCP Cub. A 723' I
Yes Yes
^"
RC-HSS-12 723' RC-HSS-13 735' g
RC-IISS-14 735' SI-HSS-412 SI RCP Cub. A 732' y
SI-ilSS-413 732' g
SI-ilSS-415 738' PS-243-VS-1 RC 725' VS-357-1 719' SI-ilSS-416 SI RCP Cub. B 730' SI-ilSS-417 730' SI-HSS 419 738' SI-HSS-117 737' SI-ilSS'118 737' E
PS-244 VS-1 RC 725' VS-35 1 719' 5
RC-IISS-1 RC RCP Cub.-C 734'
.I Yes Yes RC-IISS-2 734' E
Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that safety evaluations, documentation and reporting are.provided in accordance with 10 CFR 50.59 and R
that a revision to Table 3.7-4 is included with'a subsequent License Amendment request.
TABLE 3.7-4a (Continued) g SAFETY RELATED llYDRAULIC SNUBBERS
- N
~
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR llIGil RADIATION ESPECIALLY DIFFICULT N0.
ON, LOCATION AND ELEVATION i
INACCESSIBLE ZONE TO REMOVE E
RC-IISS-3 RC RCP Cub. C 722' I
Yes Yes RC-IISS-4 722' E
PS-245-VS-1 725' VS-359-1 719' SI-IISS-420 SI 731' SI-HSS-421 731' RC-IISS-101 RC RCP Cub. A.
739' I
Yes Yes RC-IISS-102 739' SI-ilSS-102A SI 745' SI-ilSS-102B 745' R
SI-ilSS-414 741' RC-IISS-103 RC RCP -Cub. B 739'
'l 7
RC-IISS-104 739' M
SI-ilSS-418 SI 741' RC-IISS-23 RC REA. CONT. BLDG.
749' A
No No I
RC-IISS-105 RC RCP Cub. C 739' I
Yes Yes RC-IISS-106 RC 739' RC-IISS-130 739' I
RC-IISS-131 739' SI-ilSS-114A SI 745' SI-ilSS-114B 745'
> SI-IISS-422 741' Po SI-ilSS-423 739' 5.l RC-IISS-22 RC Pressurizer Cub.
784' A
Yes Yes RC-IISS-41A 784' r
5
(
- Snubbers may. be added to safety related systems without prior License Amendment to Table 3.7-4 prov'ded that safety evaluations, documentation and reporting are provided in accordance with 10 CFR 50.59 an.1 ea-g that a revision to Table 3.7-4 is included with a subsequent License Amendment request.
TABLE 3.7-4a (Continued)
SAFETY RELATED flYDRAULIC SNUBBERS
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE TO REMOVE FQ RC-liSS-44A RC Pressurizer Cub.
784' A
Yes Yes RC-IISS-302 784' RC-IISS-303A 784' a
c-5 RC-IISS-3038 784' RS-IISS-235 RS REA. CONT. BLDG.
832' I
No RS-IISS-210 817' RS-IISS-211 817' RS-IISS-213 800' RS-IISS-214 800' RS-IISS-222 814' i
RS-IISS-223 814' w2 RS-IISS-224 813' RS-IISS-225 813' y
d, WFPD-IISS-201 FW 780' A
No E'-
WFPD-IISS-202 "
780' SilP-HSS-201 MS 805' I
Yes SilP-ilSS-202 805' SilP-ilSS-203 805' SilP-ilSS-204 805' WFPD-IISS-203 FW 780' A
No WFPD-IISS-204 "
780' p
WFPD-ilSS-205 "
780' a
g WFPD-IISS-206 "
780' a
g-SilP-ilSS-205 MS 798' I
Yes g
SilP-ilSS-206 798' r
5 Snubbers may..be added to safety related systems without prior License Amendment to Table 3.7-4 provided that safety evaluations, documentation and reporting are provided in accordance with 10 CFR 50.59 and that a revision to Table 3.7-4 is included with a subsequent License Amendment request.
.g -
),
to i
9' TABLE 3.7-4a (Continued)
SAFETY RELATED IIYDRAULIC SNUBBERS
- E e
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR IIIGil RADIATION ESPECIALLY DIFFICliLT
[
-NO.
ON, LOCATION AND ELEVATION
! INACCESSIBLE ZONE TO REMOVE i-Q WFPD-IISS-207 W REA. CONT. BLDC.
772' A
No No e WFPD-IISS-208
.772' WFPD-HSS-208A
.771' SIIP-ilSS-207 MS 796' I
Yes S11P-IISS-208 796' WFPD-IISS-211 m
772' A
No WFPD-IISS-212 772' WFPD-IISS-212A 771' i
SIIP-ilSS-213 MS 798' I
yes SilP-ilSS-214 798' 798' S!!P-ilSS-209 SilP-ilSS-210 798' 798' SilP-IISS-211 SilP-IISS-212 798' SHP-ilSS-214A 805' WFPD-IISS-209 m
780' A
No u WFPD-IISS-210 780'
~
D RC-IISS-128 RC 734'
't es u RC-IISS-129 734' a
d,.RC-HSS-119 734'
$ SI-PSSP-337 SI 728' No SI-ilSS-409 729' SI-HSS-410' 731' a
SI-ilSS-411 731' RS-IISS-201 RS 731' YCG
- Snubbers may be added to safety related systems without prior License Admendment to Table 3.7-4 provided r*
that safety evaluations, documentation and reporting are provided in accordance with 10CFR 50.59.and that a revision to Table 3.7-4 is included with a subsequent License Amendment request.
E i
to j-i
l I
TABLE 3.7-4a (Continued) g SAFETY RELATED flYDRAULIC SNUBBERS
- E m"
SNUBBER SYSTEM SNUBBER INSTALL.ED ACCESSIBLE OR HIGil RADIATION ESPECIALLY DIFFICULT
- p NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE TO REMOVE m
RS-IISS-202 RS REA. CONT. BLDG.
731' A
Yes No RS-IISS-237 731' No a
55 RS-IISS-238 731' RS-IISS-229 731' RS-IISS-236 731' RS-IISS-234 726' CC-IISS-405A 707' I
Yes Yes CC-IISS-405B 707' CC-IISS-407A 711' CC-IISS-4078 711' RS-IISS-205 RS 702' A
No No R
RS-IISS-206 702' RS-IISS-219 702'
?
RS-IISS-220 702' M
RS-HSS-207 702' RS-IISS-208 702' RS-HSS-209 710' RS-HSS-215 715' RS-IISS-216 715' Ril-HSS-105 Ril 704' I
yes yes Ril-HSS-107 704' g
Ril-HSS-108 704' g
Ril-IISS-lli 704' g.
Ril-HSS-ll 3 710' g
Ril-HSS-I l4 710' l
F 5
Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided
~
that safety evaluations, documentation and reporting are provided in accordance with 10 CFR 50.59 and that a revision to Table 3.7-4 is included with a subsequent License Amendment request.
t i
i TABLE 3.7-4a (Continued)
SAFETY RELATED llYDRAULIC SNUBBERS
ACCESSIBLE OR llIGil RADIATION ESPECIALLY DIFFICULT j
N0.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE TO REMOVE l.
F CC-ilSS-404 CC REA. CONT. BLDG.
711' A
Yes No O
CC-IISS-408 711' I
Ril-llSS-101 RH 704' A
No Ril-llSS-102 704' A
E Ril-HSS-402 708' Q
Ril-llSS-403 708' RH-HSS-121 699' RH-ilSS-122 699' RS-IISS-203 RS 701' RS-IISS-221 702' CC-IISS-401 CC P.A. BLDG.
736' i
CC-IISS-402 736' CC-IISS-403 736' CC-IISS-404 745' Yes I
CC-HSS-405 742' No CC-PSSP-301 724' WR-ilSS-310 RW 731' CH-HSS-30S CH 720' SI-ilSS-309 SI 720' I
Yes CH-ilSS-311 CH 741' Yes WR-ilSS-311 RW 724' A
No No WR-ilSS-312 724' j
WR-HSS-313 724' i
R WR-ilSS-314 731' WR-ilSS-301 CABLE VAULT 730' 7'
WR-ilSS-302 730' M
.I t'
a i
g
- Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that safety evaluations, documentation and reporting are provided in accordance with 10 CFR 50.59 and E
that a revision to Table 3.7-4 is included with a subsequent License Amendment request.
Et 0
,t -
TABLE 3.7-4a (Continued)
~
9
_g SAFETY RELATED HYDRAULIC SNUBBERS *
<E SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT h
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE TO REMOVE WR-HSS-303A RW CABLE VAULT 731' A
No No E
WR-HSS-3038 731' U
WR-HSS-304A 728' WR-HSS-3048 728' WR-HSS-316 733' WR-HSS-306
.733' WR-HSS-308 731' WR-ilSS-309 731' e
WR-HSS-300 724' SI-HSS-522 SI 731' SI-HSS-523A 731' SI-ilSS-5238 731' SI-HSS-521 731' SI-HSS-516A 731' SI-ilSS-516B 731' SI-HSS-520 731' SI-HSS-515 731' SI-HSS-519 731' m2 SI-HSS-514 731' SI-HSS-512 738'
"~
y L
SI-HSS-512A 734' y
SI-HSS-Sil 738' SI-HSS-518 733' a
SI-HSS-517 738 p
QS-HSS-504 QS SAFEGUARDS AREA 741' E
g a
a i,
g
- Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that safety evaluations, documentation and reporting are provided in accordance with 10 CFR 50.59 and O
that a revision to Table 3.7-4 is indluded with a subsequent License Amendment request.
- }
TABLE 3.7-4a (C:ntinu:d)
SAFETY RELATED llYDRAULIC SNUBBERS
ON, LOCATION AND ELEVATI0ft INACCESSIBLE ZONE TO REMOVE E
QS-PSSP-501 QS SAFEGUARDS AREA 734' A
No No SI-PSSP-002 SI 743' SI-PSSP-003 743' E
SI-PSSP-009 743' I
U SI-PSSP-010 743' SI-PSSP 067C "
743' SI-PSSP-060D "
743' SI-PSSP-033A "
753' SI-PSSP 036A "
753' i
QS-IISS-205A QS 735' QS-IISS-205B 735' QS-IISS-202 737' M
SI-ilSS-212A SI 737'
^
SI-IISS-212B 734' d
RS-IISS-210A RS SAFEGUARDS AREA 736'
- I i
!?
RS-IISS-209A 736' Ril-IISS-203 Ril 736' Ril-llSS-204A 736' Ril-flSS-204B 736' i;
I l
.E, h
- Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that safety evaluations, documentation and reportin9 are provided in accordance with 10 CFR 50.59 and that a revision to Table 3.7-4 is included with a. subsequent License Amendment request.
E I
p
a TABLE 3.7-4a (Continued)
SAFETY RELATED llYDRAULIC SNUBBERS
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE TO REMOVE l-Q FC-IISS-201 FC FUEL BUILDING 747' A
No No FC-HSS-5A 747' FC-IISS-202 745' c-2 FC-IISS-203 745' FC-IISS-204 742' FC-IISS-205 742' FC-IISS-206 742' I
M a
7' k!
\\
e E
E E
e
.o i
Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that safety evaluations, documentation and reporting are provided in accordance with 10 CFR 50.59 and that a revision to Table 3.7-4 is included with a subsequent License Amendment request.
O i
TABLE 3.7-4b bh SAFETY RELATED MECHANICAL SNUBBERS
- i 9
-=
l EI SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT
~
Ej NO.
ON,LOCATIONANDELEVATION[
INACCESSIBLE 70NE **
TO REMOVE RC-PSSP-301 RC Pressurizer Cub.
784' I
Yes Yes EE CC-PSSP-300A CC P.A. BLDG.
726' A
No No U
CC-PSSP-3008 CC 726' CC-HSS-406A CC Pipe Annulus-710' I
Yes Yes CC-HSS-406B CC 710' WR-HSS-307 RW P.A. BLDG.
732' A
No No a
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Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4b provided that a revision to Table 3.7-4b is included with the next License Amendment request.
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- Modifications to this column due to changes in high radiation areas may be made without prior nA j;
License Amendment provided that a revision to Table 3.7-4b is included with the next License Anendment request.
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PLANT SYSTEMS BASES 3/4.7.12 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other similar event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefo re, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
When the cause cf the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation and vibration.
When a snubtfr is found inoperable, an engineering evaluation is per-formed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a signifi-cant effect or degradation on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at refueling or 18 month intervals not to exceed two (2) years.
Observed failures of these sample snubbers shall require functional testing of additional units.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
Amendment No. I 49 BEAVER VALLEY - UNIT 1 B3/4 7-6
PLANT SYSTEMS' BASES 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 monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
BEAVER VALLEY - UNIT 1 B 3/4 7-6a Amendment No. 49
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ADMINISTRATIVE CONTROLS C
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Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
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Records of meetings of the OSC and the ORC.
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Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.
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Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7-4a and 3.7-4b including the date at which the service life commences and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20:
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Each High Radiation Area in which the intesity of radiation a.
is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a
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Radiation Work Peimit and any individual or group of individ-uals permitted to enter such areas shall be provided with a ra' diation monitoring device whi.ch continuously indicates the radiation dose rate in the area-.
3 b.
Each High Radiation Area in which the intensity of radiation 1s greater than 1000 mrem /hr shall be subject to the provisions of 6.12.la above, and in addition locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty.
6.13 ENVIRONMENTAL QUALIFICATION 6.13.1 By no later than June 30, 1982 all safe'ty-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors " Guidelines for Evalu-ating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979 Copies of these documents are attached to Order for Modification of License No. DPR-66 dated October 24, 1980.
BEAVER VALLEY - UNIT 1 6-19 Order dated October 24, 1980
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Amendment No., 49
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