ML18086A844
| ML18086A844 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/28/1981 |
| From: | Meyer G, Ross W Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8108070008 | |
| Download: ML18086A844 (6) | |
Text
Docket Nos. 50-272
- and 50-31 l
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
'*JUL.2. B rn 81 GMeyer LitENSEE:
Public Service Electric and Gas OELD IE-3 FACILITY:
SALEM UNITS 1 AND 2 CParrish ACRS-10
SUMMARY
OF MEETING HELD ON JUNE 30 - JULY 1, ~981 WITH LlCENSEE TO DISCUSS OUTSTANDING TECHNICAL SPECIFICATION CHANGE REQUESTS A ~eeting between the project managers of Salem Units l and 2 and representatives of the licensee was convened to review several parts of the Technical Specifications of these units where the requirements differed between plants or changes were under ~taff review.
A list of attendees is enclosed.
Ji The technical specifications under discussion related primarily to those submitted by tJ1*e licensee in response-to Lessons Learned Category A requirements for Unit 1 and to several subjects that had been discussed but not resolved during a meeting related to Unit 2 held between the licensee and staff on-*March 26, 1981.
A.
Salem-2 TS 3.1.3.2.2 J
Unit 1 does not have this TS, which *establishes requirements for the rod position indication while shutdown. The licensee has interpreted this TS to require an imniediate opening of reactor trip breakers if a rod position indication is not within +/-12 steps for each shutdown rod when the plant is in Modes 3,4, and 5. The staff explained that the i'ntent of this TS was to require that the operator have available an indication of general position and movement of all rods not fully inserted. It was not jntended that this be interpreted as a precise alignment requirement. To clarify thjs the licen-see 0ill submit a revision to this TS to (1) provide a del~y. before the trip breakers are opened, to allow time to determine the reason for the indicated misalignment ~nd/or (2) increase the limits tb more than +12 steps.
B.
TS 3.3.l Action Item 1 This subject was originally discussed at the March 26, 1981 meeting.
The licensee's procedure for surveillance testing of some of the reactor trip system instrumentation requires more than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to complete.
The W procedure requires""'0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
The TS of Units land 2 allow l'hour and-2 h_ours, I
respectively. Additionally, the Unit 2 TS requires one (of two) channels
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to be OPERABLE before the second channel may be bypassep f6r surveillance testing.
The staff will provide the licensee with additional guidance for preparation of TS revisions that provide sufficient time to complete the C:: l I Y' \\Hl i l l ::> n t;:',';' t e S t i n g,
8108070008 810728 PDR ADOCK 05000272 P
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( C.
TS 3.3.2 ESF Actuation System Instrumentation Unit 2 has requirements related to AFW that are different from TS that have been proposed for Unit 1.
The licensee proposes to submit rev1s1ons for Tables 3.3-3, 3.3-4, 3.3-5 and 4.3-2 that require the following:
(1)
Actuation of AFW pumps upon Station Blackout.
(2)
For Unit 1 - Actuation of AFW motor dri.ven pumps upon trip of both main feedwater pumps The 1 icensee requests that the requirement for channel functional tests *for
- trip of main feedwater pumps each 92 days be changed to the 18 months schedule applicable to testing AFW pumps.
The staff will provide guidance on this subject.
Table 4.3-2 for Uni_t 1. *-A monthly functional test will be required for 11start of AFW pumps upon RCP undervol tage.
11 Proposed Table 3.3-5 for Unit 1 (ESF Response Time) will be revised to indicate a ~ 60 seconds response time for all actuations of the motor driven AFW pumps.
The licensee requested approval of a::: 15.0 seconds response time (for Unit 1) for isolation of purge and exhaust valves upon containment high radioactivity signal.
Additional justification will be provided.
A response time of~ 20.0 seconds is requested for Unit 2 so as to include the recount time that is part of the actuation logic.
The staff considered these requests to be logical and will review them in greater depth upon re~eipt of ba~kup information.
D.
Salem-2 TS 3.3.3.l (Radiation Monitoring Instruments)
Action 24 should reference TS 3.4.7.l rather than TS 3.4.6.l.
The staff will issue a corrected page.
E.
Salem-1 TS 3.4.4 (Surveillance of Pressurizer)
The licensee proposes to submit a revision of this TS that is identical to the requirements for Unit 2.
F.
TS 3.3.3.7 Accident Monitoring Instrumentation The licensee has submitted new Tables 3.3-lla and 3.3-llb for Unit 1; These Tables differ in format and contents from Table 3.3-11 that was approved fo~ l
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for Unit 2.
The staff advised the licensee that Regulatory Guide *1.97 (Rev 2) should be the basis for determining which instruments should be listed in this Table.
The licensee proposes to revise Tables 3.3-lla, 3.3-llb and 4.3-11 for both units to cover the following sub-items:
Tables 3.3-lla and 3.3-llb (9)
Boric Acid Tank Soluti*on Level Action 2 (return to operable in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) applies when the number of operable channels is less than one.
(Unit 1 has 1 channel on each of two tanks)
(10) AFW Flow Rate A new Action 5 (return to operable in 7 days) applies when the number of operable channels is less than the minimum (one per each*
of 3 steam generators). Staff agreed one channel could be lost for an unlimited time if the wide range level indicator is available for the affected~steam generator.
(11) RCS Subcooling Margin Monitor.
The plant has one computer for this use and backup capability consisting of steam tables; therefore, the 11 Total Number of Channels 11 is considered to be two.
New action statements will be written by the licensee to (a) provide 7 days to make the computer operable, and* (b) describe the basis for listing the minimum number of channels as one.
. (12, 13, and 14) Valve Position Indicators The PORV, PORV Block Valve, and Pressurizer Safety Valves each have one position indicating channel.
A second means of determining the position of these valves will be described in a supplementary submittal by the licensee.
The loss of one of these indicators will initiate Action 1 (7 days to make operable).
The loss of both indication will initiate Action 2 {48 hours to restore to operable condition).
Table 4.3-11
( 10) AFW Fl ow Rate - Channel wi 11 be checked each startup (12,13,14) The licensee will use surveillance of other parameters (such as tailpipe temp~rature, pressurizer relief tank wa.te.r level) to _back up the single position indicators for the PORV, PORV Block Valves, and Safety Valves. The staff will review the parameters to be proposed for approval.
4.* G. The licensee will submit a revision of TS3.8.2.3 to indicate more clearly the capability to alternate battery chargers.
H. The licensee stated that the entry in Table 2.3-3 of the Environmental TS, for i-Jaste Discharge Line, is in error. The licensee will submit a proposed.
revision.
I. Salem-2 TS 4.6.l.3.b (Containment Air Locks)
This TS requires that an overall air lock leakage test at design pressure be conducted prior to establishing CONTAINMENT INTEGRITY, if the air lock has been opened when CONTAINMENT INTEGRITY was not required.
This require-ment is not in Salem-1 TS.
The lice~see desires to have it removed from the Salem-2 TS because the frequency of testing will degrade the airlock seals.
The staff will provide guidance on this subject.
J.
Ihi s TS sets the survei ll anc_e-frequencies for determining the opera bi 1 ity of _snubbers.
The 1 icensee desires that. this require~_e~t be based qn types of snubbers rather than being inclusiv~. fhe basis f6r this position is that experience has shown that certain types of snubbers are much more prone to fail than others.
To date this failure rate has been low and considered to be caused by damage from maintenance personnel.
The staff will review this request and provide a response to the licensee.
Enclosure:
As stated cc:
See next page OFFICE. *****:*~*!df** *****tt!~~**
SURNAME. ** ** ** * * * * ** * ** * * * * * * * * * * *****, *** * ':/; ***********
DATE *
.....?.!a.'1.!.8J........... Z/J8/.BL...
NRG FORM 316 (10-60) NRCM 0240 11/~~
W. J. Ross, Project Manager Operating Reactors Branch No. l Division of Licensing
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G. Meyer, Project Manager Licensing Branch No. 3 Division of Licensing OFFICIAL RECORD COPY USGPO: 1981-335-96()
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Mr. F. \\./. Schneider Public Service Electric and Gas Company cc:
Mark J. Wetterhahn, Es qui re Conner, Moore and Corber Suite 1050 1747 Pennsylvania Avenue, NW Washington, D. C.
20006 Rich a rd Fry 1 in g, Jr., Esquire Assistant General Solicitor Public Service Electric and Gas Company 80 Park Place tiewark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Ti:-enton, New Jersey. 0.8628 _
i'rr. R. L. Mi ttl, Genera 1 Manager licensing and Environment
~ublic Service Electric and Gas Company 80 Park Plaza 17C tle1*1ark, New Jersey 07101
- ir. Henry J. Midura, Manager Salem Nuclear Generating Station Public Service Electric and Gas Company P. 0. Box 168 Hancocks Bridge, ~!ew Jersey 08038 Salem Free library 112 ~est Broadway Sal em, Nevi Jersey 08079 Leif J. Norrholm, Resident Inspector Salen Nuclear Generating Station U. S. Nuclear Regulatory Commission Drav1er I Hancocks Bridge, Nevi Jersey 08038 John M. Zupko, Jr., Manager Nuclear Operations Support Public Service Electric and Gas Company 80 Park Plaza - 15A
~!ewark, l*~ew Jersey 07101 Mr. R. A. Udiritz General Man~ger, Nuclear Production Public Service Electric and Gas Company 80 Park Plaza 15A Newark, New Jersey 07101 Mr. J. T. Boettger General Manager, Quality Assurance I&E Public Service Electric and Gas Company 80 Park Plaza
- Mewark,
~Jew Jersey 07101 Mr;-Eawin A. liden, Manager Nuciear licensing licensing and Environmental Dept.
Public Service Electric and Gas Company 8 0 P a rk P 1 a z a 1 6 D t~ewark, t~ew Jersey 07101
NRC G. Meyer
\\.~. Ross M. Virgilio R. Kendail P. Wagner J. T. Beard e *-
MEETING BEtWEEN NRC STAFF AND REPRESENTATIVES OF PUBLIC SERVICE ELECTRIC AND GAS COMPANY 6/30/81 - 7 /1 /81 ATTENDEES PSE&G R. Bec.kwi th*
J. Ronafalvy G. Kapp J